ML18128A201
ML18128A201 | |
Person / Time | |
---|---|
Site: | Susquehanna |
Issue date: | 04/25/2018 |
From: | Susquehanna |
To: | Document Control Desk, Office of Nuclear Reactor Regulation |
References | |
Download: ML18128A201 (88) | |
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- MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2018-8409 USER INFORMATION:
GERLACH*ROSEY M EMPL#: 028401 CA#: 0363 Address: NUCSA2 Phone#: 542-3194 TRANSMITTAL INFORMATION: TO: GERLACH*ROSEY M 04/25/2018 LOCATION: USNRC FROM: NUCLEAR RECORDS DOCUMENT CONTROL CENTER (NUCSA-2) THE FOLLOWING CHANGES HAVE OCCURRED TO THE HARDCOPY OR ELECTRONIC MANUAL ASSIGNED TO YOU. HARDCOPY USERS MUST ENSURE THE DOCUMENTS PROVIDED MATCH THE INFORMATION ON THIS TRANSMITTAL. WHEN REPLACING THIS MATERIAL IN YOUR HARDCOPY MANUAL, ENSURE THE UPDATE DOCUMENT ID IS THE SAME DOCUMENT ID YOU'RE REMOVING FROM YOUR MANUAL. TOOLS FROM THE HUMAN PERFORMANCE TOOL BAG SHOULD BE UTILIZED TO ELIMINATE THE CHANCE OF ERRORS . TENTION: "REPLACE" directions do not affect the Table of Contents, Therefore no
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TRMl - TECHNICAL REQUIREMENTS MANUAL UNIT 1 REMOVE MANUAL TABLE OF CONTENTS DATE: 04/11/2018 ADD MANUAL TABLE OF CONTENTS DATE: 04/24/2018 CATEGORY: DOCUMENTS TYPE: TRMl ID: TEXT 3.2.1 ADD: REV: 18 REMOVE: REV:17
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- CATEGORY: DOCUMENTS ID: TEXT LOES ADD: REV: 93 TYPE: TRMl REMOVE: REV:92 ANY DISCREPANCIES WITH THE MATERIAL PROVIDED, CONTACT DCS@ X3107 OR X3171 FOR ASSISTANCE. UPDATES FOR HARDCOPY MANUALS WILL BE DISTRIBUTED WITHIN 3 DAYS IN ACCORDANCE WITH DEPARTMENT PROCEDURES. PLEASE MAKE ALL CHANGES AND ACKNOWLEDGE COMPLETE IN YOUR NIMS INBOX UPON COMPLETION OF UPDATES. FOR ELECTRONIC MANUAL USERS, ELECTRONICALLY REVIEW THE APPROPRIATE DOCUMENTS AND ACKNOWLEDGE COMPLETE IN YOUR NIMS INBOX .
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. a n u a l T:i.tle: TECHNICAL REQUIREMENTS MANUAL UNIT 1 Table Of Contents Issue Date: 04/24/2018 Procedure Name Rev Issue Date Change ID Change Number TEXT LOES 93 04/24/2018 Title~ LIST OF EFFECTIVE SECTIONS TEXT TOC 25 04/28/2015
Title:
TABLE OF CONTENTS TEXT 1.1 1 01/31/2014 /\.
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USE AND APPLICATION DEFINITIONS ,.,//
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PLANT PROGRAMS AND
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REACTIVITY
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Title:
REACTIVITY\CON1R?L SYSTEMS CONTROL ROD DRIVE (CRD) HOUSING SUPPORT
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Title:
REACTIVITY CONTROL SYSTEMS CONTROL ROD BLOCK INSTRUMENTATION TEXT 3.1.4 0 11/18/2002
Title:
REACTIVITY CONTROL SYSTEMS CONTROL ROD SCRAM ACCUMULATORS INSTRUMENTATION & CHECK VALVE TEXT 3.2.1 18 04/24/2018
Title:
CORE OPERATING LIMITS REPORT (COLR) Pagel of 16 Report Date: 04/24/18
SSES MANUAL Manual Name: TRMl
* '{anual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 0 11/18/2002 TEXT 3.3.1
Title:
INSTRUMENTATION RADIATION MONITORING INSTRUMENTATION TEXT 3.3.2 3 03/31/2011
Title:
INSTRUMENTATION SEISMIC MONITORING INSTRUMENTATION TEXT 3.3.3 2 11/09/2007
Title:
INSTRUMENTATION METEOROLOGICAL MONITORING INSTRUMENTATION TEXT 3.3.4 11 06/29/2017
Title:
INSTRUMENTATION TRM POST-ACCIDENT MONITORING INSTRUMENTATION TEXT 3.3.5 0 11/18/2002
Title:
INSTRUMENTATION THIS PAGE INTENTIONALLY LEFT BLANK f'., ,_ ,~EXT 3.3 .6 4 04/29/2014
Title:
INSTRUMENTATION TRM ISOLATION ACTUATION INSTRUMENTATION TEXT 3.3.7 2 11/10/2015
Title:
INSTRUMENTATION MAIN TURBINE OVERSPEED PROTECTION SYSTEM TEXT 3.3.8 1 10/22/2003
Title:
INSTRUMENTATION INTENTIONALLY LEFT BLANK TEXT 3.3.9 3 04/17/2008
Title:
OPRM INSTRUMENTATION CONFIGURATION TEXT 3.3.10 1 12/14/2004
Title:
INSTRUMENTATION REACTOR RECIRCULATION PUMP MG SET STOPS TEXT 3.3.11 1 10/22/2003
Title:
INSTRUMENTATION MVP ISOLATION INSTRUMENTATION TEXT 3.3.12 1 03/05/2015 Page I
Title:
WATER MONITORING INSTRUMENTATION of 16 Report Date: 04/24/18
SSES MANUAL Manual Name: TRMl -~nual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 3.4.1 1 04/26/2006
Title:
REACTOR COOLANT SYSTEM REACTOR COOLANT SYSTEM CHEMISTRY TEXT 3.4.2 1 04/16/2009
Title:
REACTOR COOLANT SYSTEM INTENTION~.LLY LEFT BLAL~K TEXT 3.4.3 1 11/09/2007
Title:
REACTOR COOLANT SYSTEM HIGH/LOW PRESSURE INTERFACE LEAKAGE MONITORS TEXT 3.4.4 2 04/17/2008
Title:
REACTOR COOLANT SYSTEM REACTOR RECIRCULATION FLOW AND ROD LINE LIMIT TEXT 3.4.5 1 04/26/2006
Title:
REACTOR COOLANT SYSTEM REACTOR VESSEL MATERIALS .'EXT 3 .4.6 2 04/25/2013
Title:
REACTOR RECIRCULATION SINGLE LOOP OPERATION SLO FLOW RATE RESTRICTION TEXT 3.5.1 1 02/04/2005
Title:
EMERGENCY CORE COOLING AND RCIC ADS MANUAL INHIBIT TEXT 3.5.2 1 11/09/2007
Title:
EMERGENCY CORE COOLING AND RCIC ECCS AND RCIC SYSTEM MONITORING INSTRUMENTATION TEXT 3.5.3 0 11/18/2002
Title:
EMERGENCY CORE COOLING AND RCIC LONG TERM NITROGEN SUPPLY TO ADS TEXT 3.6.1 0 11/18/2002
Title:
CONTAINMENT VENTING OR PURGING TEXT 3.6.2 2 04/29/2014
Title:
SUPPRESSION CHAMBER TO DRYWELL VACUUM BREAKER POSITION INDICATION TEXT 3.6.3 0 11/18/2002
Title:
CONTAINMENT SUPPRESSION POOL ALARM INSTRUMENTATION Pagel of 16 Report Date: 04/24/18
SSES MANUAL Manual Name: TRMl
{anual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 3.6.4 0 11/18/2002
Title:
CONTAINMENT PRIMARY CONTAINMENT CLOSED SYSTEM BOUNDARIES TEXT 3.7.1 0 11/18/2002
Title:
PLANT SYSTEMS EMERGENCY SERVICE WATER SYSTEM (ESW) SHUTDOWN TEXT 3.7.2 0 11/18/2002
Title:
PLANT SYSTEMS ULTIMATE HEAT SINK (UHS) AND GROUND WATER LEVEL TEXT 3.7.3.1 4 02/16/2017
Title:
PLANT SYSTEMS FIRE SUPPRESSION WATER SUPPLY SYSTEM TEXT 3.7.3.2 3 04/16/2009
Title:
PLANT SYSTEMS SPRAY AND SPRINKLER SYSTEMS
~~iifXT 3.7.3.3 4
Title:
PLANT SYSTEMS CO2 SYSTEMS TEXT 3.7.3.4 2 05/16/2016 04/16/2009
Title:
PLANT SYSTEMS HALON SYSTEMS TEXT 3.7.3.5 2 04/16/2009
Title:
PLANT SYSTEMS FIRE HOSE STATIONS TEXT 3.7.3.6 2 04/16/2009
Title:
PLANT SYSTEMS YARD FIRE HYDRANTS AND HYDRANT HOSE HOUSES TEXT 3.7.3.7 1 04/26/2006
Title:
PLANT SYSTEMS FIRE RATED ASSEMBLIES TEXT 3.7.3.8 13 12/18/2017
Title:
PLANT SYSTEMS FIRE DETECTION INSTRUMENTATION TEXT 3.7.4 1 04/26/2006
Title:
PLANT SYSTEMS SOLID RADWASTE SYSTEM Page_! of 16 Report Date: 04/24/18
SSES MANUAL Manual Name g TRMl ~anual Titleg TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 3.7.5.1 1 03/05/2015
Title:
PLANT SYSTEMS MAIN CONDENSER OFFGAS HYDROGEN MONITOR TEXT 3.7.5.2 0 11/18/2002
Title:
PLANT SYSTEMS MAIN CONDENSER OFFGAS EXPLOSIVE GAS MIXTURE TEXT 3.7.5.3 l 04/26/2006
Title:
PLANT SYSTEMS LIQUID HOLDUP TANKS TEXT 3.7.6 3 06/04/2012
Title:
PLANT SYSTEMS ESSW PUMPHOUSE VENTILATION TEXT 3.7.7 2 09/05/2008
Title:
PLANT SYSTEMS MAIN CONDENSER OFFGAS PRETREATMENT LOGARITHMIC RADIATION MONITORING ~EXT 3.7.8 5 03/05/2015
Title:
PLANT SYSTEMS SNUBBERS TEXT 3.7.9 2 01/31/2014
Title:
PLANT SYSTEMS CONTROL STRUCTURE HVAC TEXT 3.7.10 1 12/14/2004
Title:
PLANT SYSTEMS SPENT FUEL STORAGE POOLS (SFSPS) TEXT 3.7.11 0 04/16/2009
Title:
STRUCTURAL INTEGRITY TEXT 3.8.1 2 04/05/2010
Title:
ELECTRICAL POWER PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES TEXT 3.8.2.l 2 11/09/2007
Title:
ELECTRICAL POWER MOTOR OPERATED VALVES (MOV) THERMAL OVERLOAD PROTECTION - CONTINUOUS TEXT 3.8.2.2 2 12/14/2004
Title:
ELECTRICAL POWER MOTOR OPERATED VALVES (MOV) THERMAL OVERLOAD PROTECTION - AUTOMATIC Page~ of 16 Report Date: 04/24/18
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Title:
ELECTRICAL POWER DIESEL GENERATOR (DG) MAINTENANCE ACTIVITIES TEXT 3.8.4 0 11/18/2002
Title:
ELECTRICAL POWER 24 VDC ELECTRICAL POWER SUBSYSTEM TEXT 3.8.5 1 11/14/2013
Title:
ELECTRICAL POWER DEGRADED VOLTAGE PROTECTION TEXT 3.8.6 1 12/08/2011
Title:
ELECTRICAL POWER EMERGENCY SWITCHGEAR ROOM COOLING TEXT 3.8.7 1 06/15/2009
Title:
BATTERY MAINTENANCE AND MONITORING PROGRAM
.***~:EXT 3.9.1 0
Title:
REFUELING OPERATIONS DECAY TIME TEXT 3.9.2 0 11/18/2002 11/18/2002
Title:
REFUELING OPERATIONS COMMUNICATIONS TEXT 3.9.3 0 11/18/2002
Title:
REFUELING OPERATIONS REFUELING PLATFORM TEXT 3.10.1 1 04/26/2006
Title:
MISCELLANEOUS SEAL SOURCE CONTAMINATION TEXT 3.10.2 2 08/08/2006
Title:
MISCELLANEOUS SHUTDOWN MARGIN TEST RPS INSTRUMENTATION TEXT 3.10.3 2 06/15/2010
Title:
MISCELLANEOUS INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI) 04/17/2008 TEXT 3.10.4 2
Title:
INTENTIONALLY LEFT BLANK Page .§. of 16 Report Date: 04/24/18
SSES MANUAL Manual Name: TRMl ~anual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 3.11.1.1 1 04/26/2006
Title:
RADIOACTIVE EFFLUENTS LIQUID EFFLUENTS CONCENTRATION TEXT 3 . 11. 1. 2 1 04/26/2006
Title:
RADIOACTIVE EFFLUENTS LIQUID EFFLUENTS DOSE TEXT 3 . 11 . 1. 3 1 04/26/2006
Title:
RADIOACTIVE EFFLUENTS LIQUID WASTE TREATMENT SYSTEM TEXT 3
- 11 . 1. 4 2 10/09/2012
Title:
RADIOACTIVE EFFLUENTS LIQUID RADWASTE EFFLUENT MONITORING INSTRUMENTATION TEXT 3 . 11. 1. 5 3 03/05/2015
Title:
RADIOACTIVE EFFLUENTS RADIOACTIVE LIQUID PROCESS MONITORING INSTRUMENTATION ~~EXT 3.11.2.1 3 04/26/2006
Title:
RADIOACTIVE EFFLUENTS DOSE RATE TEXT 3.11.2.2 1 04/26/2006
Title:
RADIOACTIVE EFFLUENTS DOSE - NOBLE GASES TEXT 3.11.2.3 1 04/26/2006
Title:
RADIOACTIVE EFFLUENTS DOSE - IODINE, TRITIUM, AND RADIONUCLIDES IN PARTICULATE FORM TEXT 3.11.2.4 0 11/18/2002
Title:
RADIOACTIVE EFFLUENTS GASEOUS RADWASTE TREATMENT SYSTEM TEXT 3.11.2.5 4 07/03/2013
Title:
RADIOACTIVE EFFLUENTS VENTILATION EXHAUST TREATMENT SYSTEM TEXT 3 .11. 2. 6 8 06/29/2017
Title:
RADIOACTIVE EFFLUENTS RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION TEXT 3.11.3 1 04/26/2006
- ~ :
Title:
RADIOACTIVE EFFLUENTS TOTAL DOSE Page J_ of 16 Report Date: 04/24/18
SSES MANUAL Manual Name: TRMl
~anual Titleg TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 3 . 11. 4 . 1 5 03/05/2015
Title:
RADIOACTIVE EFFLUENTS MONITORING PROGRAM TEXT 3.11.4.2 2 04/26/2006
Title:
RADIOACTIVE EFFLUENTS LAND USE CENSUS TEXT 3 . 11. 4 . 3 1 04/26/2006
Title:
RADIOACTIVE EFFLUENTS INTERLABORATORY COMPARISON PROGRAM TEXT 3.12.1 0 11/19/2002
Title:
LOADS CONTROL PROGRAM CRANE TRAVEL-SPENT FUEL POOL STORAGE POOL TEXT 3.12.2 4 04/17/2008
Title:
LOADS CONTROL PROGRAM HEAVY LOADS REQUIREMENTS
.,.,EXT 3 .12 .3 0 11/19/2002
Title:
LOADS CONTROL PROGRAM LIGHT LOADS REQUIREMENT TEXT 4.1 0 08/31/1998
Title:
ADMINISTRATIVE CONTROLS ORGANIZATION TEXT 4.2 0 08/31/1998
Title:
ADMINISTRATIVE CONTROLS REPORTABLE EVENT ACTION TEXT 4.3 0 08/31/1998
Title:
ADMINISTRATIVE CONTROLS SAFETY LIMIT VIOLATION TEXT 4.4 1 12/18/2008
Title:
ADMINISTRATIVE CONTROLS PROCEDURES & PROGRAMS TEXT 4.5 0 08/31/1998
Title:
ADMINISTRATIVE CONTROLS REPORTING REQUIREMENTS TEXT 4.6 0 08/31/1998
Title:
ADMINISTRATIVE-CONTROLS RADIATION PROTECTION PROGRAM Page _§. of 16 Report Date: 04/24/18
SSES MANUAL Manual Name: TRMl ~~nual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 4.7 0 08/31/1998
Title:
ADMINISTRATIVE CONTROLS TRAINING TEXT B3.0 5 03/05/2015
Title:
APPLICABILITY BASES TECHNICAL REQUIREMENT FOR OPERATION (TRO) APPLICABILITY TEXT B3.l.1 2 04/29/2014
Title:
REACTIVITY CONTROL SYSTEMS BASES ANTICIPATED TRANSIENT WITHOUT SCRAM ALTERNATE ROD INJECTION (ATWS-ARI) INSTRUMENTATION TEXT B3.l.2 0 11/19/2002
Title:
REACTIVITY CONTROL SYSTEMS BASES CONTROL ROD DRIVE (CRD) HOUSING SUPPORT TEXT B3 .1.3 4 12/18/2017
Title:
REACTIVITY CONTROL SYSTEMS BASES CONTROL ROD BLOCK INSTRUMENTATION .EXT B3.l.4 0 11/19/2002
Title:
REACTIVITY CONTROL SYSTEMS BASES CONTROL ROD SCRAM ACCUMULATORS INSTRUMENTATION AND CHECK VALVE TEXT B3.2.l 0 11/19/2002
Title:
CORE OPERATING LIMITS BASES CORE OPERATING LIMITS REPORT (COLR) TEXT B3.3.l 1 01/31/2014
Title:
INSTRUMENTATION BASES RADIATION MONITORING INSTRUMENTATION TEXT B3.3.2 2 03/31/2011
Title:
INSTRUMENTATION BASES SEISMIC MONITORING INSTRUMENTATION TEXT B3.3.3 3 12/18/2008
Title:
INSTRUMENTATION BASES METEOROLOGICAL MONITORING INSTRUMENTATION TEXT B3.3.4 7 06/29/2017
Title:
INSTRUMENTATION BASES TRM POST ACCIDENT MONITORING (PAM) INSTRUMENTATION TEXT B3.3.5 2 11/09/2007
Title:
INTENTIONALLY LEFT BLANK Page~ of 16 Report Date: 04/24/18
SSES MANUAL Manual Name: TRM1
. }f;anual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT B3.3.6 5 01/31/2014
Title:
INSTRUMENTATION BASES TRM ISOLATION ACTUATION INSTRUMENTATION TEXT B3.3.7 2 11/10/2015
Title:
INSTRUMENTATION BASES MAIN TURBINE OVERSPEED PROTECTION SYSTEM TEXT B3.3.8 1 10/22/2003
Title:
INTENTIONALLY LEFT BLANK TEXT B3.3.9 3 04/17/2008
Title:
OPRM INSTRUMENTATION TEXT B3.3.10 3 08/09/2010
Title:
INSTRUMENTATION BASES REACTOR RECIRCULATION PUMP MG SET STOPS _ ""'.'.EXT B3 . 3 . 11 1 10/22/2003
Title:
INSTRUMENTATION BASES MVP ISOLATION INSTRUMENTATION TEXT B3.3.12 0 04/16/2009
Title:
WATER MONITORING INSTRUMENTATION TEXT B3.4.1 0 11/19/2002
Title:
REACTOR COOLANT SYSTEM BASES REACTOR COOLANT SYSTEM CHEMISTRY
- TEXT B3.4.2 1 04/16/2009
Title:
INTENTIONALLY LEFT BLANK TEXT B3.4.3 1 11/09/2007
Title:
REACTOR COOLANT SYSTEM BASES HIGH/LOW PRESSURE INTERFACE LEAKAGE MONITOR TEXT B3.4.4 0 11/19/2002
Title:
REACTOR COOLANT SYSTEM BASES REACTOR RECIRCULATION FLOW AND ROD LINE LIMIT TEXT B3.4.5 0 11/19/2002 j)
Title:
REACTOR COOLANT SYSTEM BASES REACTOR VESSEL MATERIALS Page 10 of 16 Report Date: 04/24/18
SSES MANUAL ManuaJ. Name: TRMl ~~nual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT B3.4.6 2 04/25/2013
Title:
REACTOR RECIRCULATION SINGLE LOOP OPERATION SLO FLOW RATE RESTRICTION TEXT B3.5.l 0 11/19/2002 Title~ ECCS AND RCIC BASES ADS MAJ.'i!UAL INHIBIT TEXT B3.5.2 1 11/09/2007
Title:
ECCS AND RCIC BASES ECCS AND RCIC SYSTEM MONITORING INSTRUMENTATION TEXT B3.5.3 1 11/09/2007
Title:
ECCS AND RCIC BASES LONG TERM NITROGEN SUPPLY TO ADS TEXT B3.6.l 0 11/19/2002
Title:
CONTAINMENT BASES VENTING OR PURGING . f X T B3.6.2 0 11/19/2002
Title:
CONTAINMENT BASES SUPPRESSION CHAMBER-TO-DRYWELL VACUUM BREAKER POSITION INDICATION TEXT B3.6.3 2 04/17/2008
Title:
CONTAINMENT BASES SUPPRESSION POOL ALARM INSTRUMENTATION TEXT B3.6.4 1 12/14/2004
Title:
CONTAINMENT BASES PRIMARY CONTAINMENT CLOSED SYSTEM BOUNDARIES TEXT B3.7.1 0 11/19/2002
Title:
PLANT SYSTEMS BASES EMERGENCY SERVICE WATER SYSTEM (SHUTDOWN) TEXT B3.7.2 0 11/19/2002
Title:
PLANT SYSTEMS BASES ULTIMATE HEAT SINK (UHS) GROUND WATER LEVEL TEXT B3.7.3.1 4 02/16/2017
Title:
PLANT SYSTEMS BASES FIRE SUPPRESSION WATER SUPPLY SYSTEM TEXT B3.7.3.2 2 04/26/2006
Title:
PLANT SYSTEMS BASES SPRAY AND SPRINKLER SYSTEMS Page 11 of 16 Report Date: 04/24/18
SSES MANUAL Manual Name: TRMl
~anual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT B3.7.3.3 0 11/19/2002
Title:
PLANT SYSTEMS BASES CO2 SYSTEMS TEXT B3.7.3.4 3 04/29/2014
Title:
PLANT SYSTEMS BASES HALON SYSTEMS TEXT B3.7.3.5 1 04/26/2006
Title:
PLANT SYSTEMS BASES FIRE HOSE STATIONS TEXT B3.7.3.6 1 04/26/2006
Title:
PLANT SYSTEMS BASES YARD FIRE HYDRANTS AND HYDRANT HOSE HOUSES TEXT B3.7.3.7 0 11/19/2002
Title:
PLANT SYSTEMS BASES FIRE RATED ASSEMBLIES
- ~"ci?EXT B3. 7. 3. 8 f~~-
3 09/27/2012
Title:
PLANT SYSTEMS BASES FIRE DETECTION INSTRUMENTATION TEXT B3.7.4 0 11/19/2002
Title:
PLANT SYSTEMS BASES SOLID RADWASTE SYSTEM TEXT B3.7.5.l 0 11/19/2002
Title:
PLANT SYSTEMS BASES MAIN CONDENSER OFFGAS HYDROGEN MONITOR TEXT B3.7.5.2 0 11/19/2002
Title:
PLANT SYSTEMS BASES MAIN CONDENSER OFFGAS EXPLOSIVE GAS MIXTURE TEXT B3.7.5.3 0 11/19/2002
Title:
PLANT SYSTEMS BASES LIQUID HOLDUP TANKS TEXT B3.7.6 4 06/04/2013
Title:
PLANT SYSTEMS BASES ESSW PUMPHOUSE VENTILATION 01/31/2008 TEXT B3.7.7 2
Title:
PLANT SYSTEMS BASES MAIN CONDENSER OFFGAS PRETREATMENT LOGARITHMIC RADIATION MONITORING INSTRUMENTATION Page 12 of 16 Report Date: 04/24/18
SSES MANUAL Manual Name: TRMl .ranual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT B3.7.8 4 01/31/2014
Title:
PLANT SYSTEMS BASES SNUBBERS TEXT B3.7.9 2 12/08/2011
Title:
PLANT SYSTEMS BASES CONTROL STRUCTURE HVAC TEXT B3.7.10 1 12/14/2004
Title:
PLANT SYSTEMS BASES SPENT FUEL STORAGE POOLS TEXT B3.7.11 1 04/14/2010
Title:
STRUCTURAL INTEGRITY TEXT B3.8.1 2 03/10/2010
Title:
ELECTRICAL POWER BASES PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES .,EXT B3.8.2.l O 11/19/2002
Title:
ELECTRICAL POWER BASES MOTOR OPERATED VALVES (MOV) THERMAL OVERLOAD PROTECTION - CONTINUOUS TEXT B3.8.2.2 1 09/17/2004
Title:
ELECTRICAL POWER BASES MOTOR OPERATED VALVES (MOV) THERMAL OVERLOAD PROTECTION - AUTOMATIC TEXT B3.8.3 0 11/19/2002
Title:
ELECTRICAL POWER BASES DIESEL GENERATOR (DG) MAINTENANCE ACTIVITIES TEXT B3.8.4 0 11/19/2002
Title:
ELECTRICAL POWER BASES 24 VDC ELECTRICAL POWER SUBSYSTEM TEXT B3.8.5 1 11/14/2013
Title:
ELECTRICAL POWER BASES DEGRADED VOLTAGE PROTECTION TEXT B3.8.6 2 12/08/2011
Title:
ELECTRICAL POWER BASES EMERGENCY SWITCHGEAR ROOM COOLING TEXT B3.8.7 *2 06/04/2013
Title:
BATTERY MAINTENANCE AND MONITORING PROGRAM Page g of 16 Report Date: 04/24/18
SSES MANUAL Manual Name: TRMl
- "!-ranual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT B3.9.1 0 11/19/2002
Title:
REFUELING OPERATIONS BASES DECAY TIME TEXT B3.9.2 0 11/19/2002
Title:
REFUELING OPERATIONS BASES COMMffi.TICATIONS TEXT B3.9.3 0 11/19/2002
Title:
REFUELING OPERATIONS BASES REFUELING PLATFORM TEXT B3.10.l 0 11/19/2002
Title:
MISCELLANEOUS BASES SEALED SOURCE CONTAMINATION TEXT B3.10.2 1 03/31/2006
Title:
MISCELLANEOUS BASES SHUTDOWN MARGIN TEST RPS INSTRUMENTATION
-~~~~EXT B3 . 10 . 3 0 11/19/2002
Title:
MISCELLANEOUS BASES INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI) TEXT B3.10.4 1 04/17/2008
Title:
INTENTIONALLY LEFT BLANK TEXT B3 .11.1.1 0 11/19/2002
Title:
RADIOACTIVE EFFLUENTS BASES LIQUID EFFLUENTS CONCENTRATION TEXT B3.11.l.2 0 11/19/2002
Title:
RADIOACTIVE EFFLUENTS BASES LIQUID EFFLUENTS DOSE TEXT B3 . 11 . 1. 3 0 11/19/2002
Title:
RADIOACTIVE EFFLUENTS BASES LIQUID WASTE TREATMENT SYSTEM TEXT B3.11.l.4 0 11/19/2002
Title:
RADIOACTIVE EFFLUENTS BASES LIQUID RADWASTE EFFLUENT MONITORING INSTRUMENTATION TEXT B3.11.l.5 0 11/19/2002
Title:
RADIOACTIVE EFFLUENTS BASES RADIOACTIVE LIQUID PROCESS MONITORING INSTRUMENTATION Page 14 of 16 Report Date: 04/24/18
SSES MANUAL Manual Name: TRMl ~anual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT B3.ll.2.l 1 12/14/2004
Title:
RADIOACTIVE EFFLUENTS BASES DOSE RATE TEXT B3.11.2.2 0 11/19/2002
Title:
RADIOACTIVE EFFLUENTS BASES DOSE - NOBLE GASES TEXT B3.11.2.3 0 11/19/2002
Title:
RADIOACTIVE EFFLUENTS BASES DOSE - IODINE, TRITIUM, AND RADIONUCLIDES IN PARTICULATES FORM TEXT B3.11.2.4 0 11/19/2002
Title:
RADIOACTIVE EFFLUENTS BASES GASEOUS RADWASTE TREATMENT SYSTEM TEXT B3.ll.2.5 5 07/03/2013
Title:
RADIOACTIVE EFFLUENTS BASES VENTILATION EXHAUST TREATMENT SYSTEM ~EXT B3.11.2.6 2 09/08/2016
Title:
RADIOACTIVE EFFLUENTS BASES RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION TEXT B3 .11. 3 0 11/19/2002
Title:
RADIOACTIVE EFFLUENTS BASES TOTAL DOSE TEXT B3.11.4.1 5 03/05/2015
Title:
RADIOACTIVE EFFLUENTS BASES MONITORING PROGRAM TEXT B3 .11. 4. 2 0 11/19/2002
Title:
RADIOACTIVE EFFLUENTS BASES LAND USE CENSUS TEXT B3 . 11. 4 . 3 0 11/19/2002
Title:
RADIOACTIVE EFFLUENTS BASES INTERLABORATORY COMPARISON PROGRAM TEXT B3.12.l 1 10/04/2007
Title:
LOADS CONTROL PROGRAM BASES CRANE TRAVEL-SPENT FUEL STORAGE POOL TEXT B3.12.2 1 12/03/2010
~
Title:
LOADS CONTROL PROGRAM BASES HEAVY LOADS REQUIREMENTS Page 15 of 16 Report Date: 04/24/18
SSES MANUAL Manual Name: TRM1
~anual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT B3.12.3 0 11/19/2002
Title:
LOADS CONTROL PROGRAM BASES LIGHT LOADS REQUIREMENTS Page 16 of 16 Report Date: 04/24/18
SUSQUEHANNA STEAM ELECTRIC STATION Rev. 93 ., LIST OF EFFE_CTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL) Section TOC Title TABLE OF CONTENTS Effective Date 04/23/2015 1.0 USE AND APPLICATION 1.1 Definitions 01/21/2014 2.0 PLANT PROGRAMS 2.1 Plant Programs 04/23/2015 2.2 Instrument Trip Setpoint Table 01/21/2014 3.0 APPLICABILITY 3.0 Technical Requirement for Operation (TRO) Applicability 02/19/2015 3.1 REACTIVITY CONTROL SYSTEMS 3.1.1 Anticipated Transient Without Scram Alternate Rod Injection 10/31/2007 (ATWS-ARI) Instrumentation 3.1.2 Control Rod Drive (CRD) Housing Support 08/31/1998 3.1.3 Control Rod Block Instrumentation 12/15/2017 3.1.4 Control Rod Scram Accumulators Instrumentation and Check Valve 02/18/1999 3.2 CORE OPERATING LIMITS REPORT
- ~ 3.2.1 3.3 3.3.1 3.3.2 3.3.3 Core Operating Limits Report INSTRUMENTATION Radiation Monitoring Instrumentation Seismic Monitoring Instrumentation Meteorological Monitoring Instrumentation 04/11/2018 07/16/1999 03/10/2011 10/31/2007 3.3.4 TRM Post-Accident Monitoring Instrumentation 06/20/2017 3.3.5 Section Not Used 3.3.6 TRM Isolation Actuation Instrumentation 04/11/2014 3.3.7 Main Turbine Overspeed Protection System 11/04/2015 3.3.8 Section Not Used 10/22/2003 3.3.9 OPRM Instrumentation Configuration 03/27/2008 3.3.10 Reactor Recirculation Pump MG Set Stops 12/03/2004 3.3.11 MVP Isolation Instrumentation 10/22/2003 3.3.12 Water Monitoring Instrumentation 02/19/2015 3.4 REACTOR COOLANT SYSTEM 3.4.1 Reactor Coolant System Chemistry 03/31/2006 3.4.2 Section Not Used 04/01/2009 3.4.3 High/Low Pressure Interface Leakage Monitors 10/31/2007 3.4.4 Reactor Recirculation Flow and Rod Line Limit 03/27/2008 3.4.5 Reactor Vessel Materials 03/31/2006 3.4.6 Reactor Recirculation Single Loop Operation (SLO) 04/25/2013 Flow Rate Restriction 3.5 EMERGENCY CORE COOLING AND RCIC 3.5.'I ADS Manual Inhibit 01/28/2005 3.52 ECCS and RCIC System Monitoring Instrumentation 10/31/2007 3.5.3 Long Term Nitrogen Supply to ADS 08/31/1998 SUSQUEHANNA - UNIT 1 TRM / LOES-1 EFFECTIVE DATE 04/11/2018
SUSQUEHANNA STEAM ELECTRIC STATION Rev. 93 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
- Section 3.6 3.6.1 3.6.2 Title CONTAINMENT Venting or Purging Suppression Chamber-to-Drywell Vacuum Breaker Position Effective Date 08/31/1998 04/16/2014 3.6.3 Suppression Pool Alarm Instrumentation 01/07/2002 3.(-5.4 Primary Containment Closed System Boundaries 12/31/2002 3.7 PLANT SYSTEMS 3.7.1 Emergency Service Water System (ESW) Shutdown 07/29/1999 3.7.2 Ultimate Heat Sink (UHS) and Ground Water Level 08/31/1998 3.7.3.1 Fire Suppression Water Supply System 01/26/2017 3.7.3.2 Spray and Sprinkler Systems 04/07/2009 3.7.3.3 CO2 Systems 05/09/2016 3.7.3.4 Halon Systems 08/02/1999 3.7.3.5 Fire Hose Station 08/02/1999 3.7.3.6 Yard Fire Hydrants and Hydrant Hose Houses 08/02/1999 3.7.3.7 Fire Rated Assemblies 03/31/2006 3.7.3.8 Fire Detection Instrumentation 12/15/2017 3.7.4 Solid Radwaste System 03/31/2006 3.7.5 Explosive Gas and Storage Tank Radioactivity Monitoring Program 3.7.5.1 Main Condenser Offgas Hydrogen Monitor 02/19/2015 3.7.5.2 Main Condenser Offgas Explosive Gas Mixture 08/31/1998
- 3.7.5.3 3.7.6 3.7.7 3.7.8 3.7.9 Liquid Holdup Tanks ESSW Pumphouse Ventilation Main Condenser Offgas Pretreatment Logarithmic Radiation Monitoring Instrumentation Snubbers Control Structure HVAC 03/31/2006 05/24/2012 09/04/2008 02/19/2015 08/16/2006 3.7.10 Spent Fuel Storage Pools (SFSPs) 12/03/2004 3.7.11 Structural Integrity 09/25/2009 3.8 ELECTRICAL POWER 3.8.1 Primary Containment Penetration Conductor Overcurrent 03/25/2010 Protective Devices 3.8.2.1 Motor Operated Valves (MOV) Thermal Overload Protection -
Continuous 10/31/2007 3.8.2.2 Motor Operated Valves (MOV) Thermal Overload Protection - Automatic 12/03/2004 3.8.3 Diesel Generator (DG) Maintenance Activities 02/19/2015 3.8.4 24 VDC Electrical Power Subsystem 04/02/2002 3.8.5 Degraded Voltage Protection 11/07/2013 3.8.6 Emergency Switchgear Room Cooling 11/30/2011 3.8.7 Battery Monitoring and Maintenance program 05/28/2009 SUSQUEHANNA - UNIT 1 TRM / LOES-2 EFFECTIVE DATE 12/15/2017
SUSQUEHANNA STEAM ELECTRIC STATION Rev.93 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
- Section 3.9 3.9.1 3.9.2 Title REFUELING OPERATIONS Decay Time Communications Effective Date 08/31/1998 08/31/1998 3.9.3 Refueling Platform 08/31/1998 3.10 MISCELLANEOUS 3.10.1 Sealed Source Contamination 03/31/2006 3.10.2 Shutdown Margin Test RPS Instrumentation 08/01/2006 3.10.3 Independent Spent Fuel Storage Installation (ISFSI) 06/10/2010 3.10.4 Section not used 03/27/2008 3.11 RADIOACTIVE EFFLUENTS 3.11.1.1 Liquid Effluents Concentration 03/31/2006 3.11.1.2 Liquid Effluents Dose 03/31/2006 3.1 'l.1.3 Liquid Waste Treatment System 03/31/2006 3.1 "l.1.4 Liquid Radwaaste Effluent Monitoring Instrumentation 10/09/2012 3.1 'l.1.5 Radioactive Liquid Process Monitoring Instrumentation 02/19/2015 3.1 *1.2.1 Radioactive Effluents Dose Rate 03/31/2006 3.1'1.2.2 Dose - Noble Gases 03/31/2006 3.1'1.2.3 Dose - Iodine, Tritium, and Radionuclides in Particulate Form 03/31/2006
- 3.1 'I .2.4 3.1'1.2.5 3.11.2.6 3.11.3 3.11.4.1 3.11.4.2 Gaseous Radwaste Treatment System Ventilation Exhaust Treatment System Radioactive Gaseous Effluent Monitoring Instrumentation Total Dose Monitoring Program Land Use Census 04/02/2002 06/18/2013 06/20/2017 03/31/2006 02/19/2015 03/31/2006 3.11.4.3 lnterlaboratory Comparison Program 03/31/2006 3.12 LOADS CONTROL PROGRAM 3.12.1 Crane Travel-Spent Fuel Storage Pool 02/05/1999 3.12.2 Heavy Loads Requirements 03/14/2008 3.12.3 Light Loads Requirements 02/05/1999 4.0 ADMINISTRATIVE CONTROLS 4.1 Organization Controls 08/31/1998 4.2 Reportable Event Action 08/31/1998 4.3 Safety Limit Violation 08/31/1998 4.4 Procedures and Programs 12/11/2008 4.5 Reporting Requirements 08/31/1998 4.5.1 Startup Reports 08/31/1998 4.5.2 Annual Reports 08/31/1998 4.5.3 Special Reports 08/31/1998 4.6 Radiation Protection Program 08/31/1998 4.7 Training 08/31/1998 SUSQUEHANNA - UNIT 1 TRM / LOES-3 EFFECTIVE DATE 12/15/2017
SUSQUEHANNA STEAM ELECTRIC STATION Rev. 93 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
- Section B 3.0 B 3.1 B 3.1.1 Title APPLICABILITY BASES REACTIVITY CONTROL SYSTEMS BASES Anticipated Transient Without Scram Alternate Rod Injection Effective Date 02/19/2015 (ATWS-ARI) Instrumentation 04/16/2014 B 3.1.2 Control Rod Drive (CRD) Housing Support 08/31/1998 B 3.1.3 Control Rod Block Instrumentation 12/15/2017 B :~.1.4 Control Rod Scram Accumulators Instrumentation and Check Valve 02/18/1999 B 3.2 CORE OPERATING LIMITS BASES Page B 3.2-1 08/31/1998 B 3.3 INSTRUMENTATION BASES Page TRM / B 3.3-1 01/21/2014 Page TRM / B 3.3-2 03/10/2011 Page TRM / B 3.3-2a 10/31/2007 Page TRM / B 3.3-3 12/11/2008 Page TRM / B 3.3-3a 10/31/2007 Page TRM / B 3.3-4 06/30/2010
,, Page TRM / B 3.3-5 Page TRM / B 3.3-5a Page TRM / B 3.3-6 Page TRM / B 3.3-7 Page TRM / B. 3.3-8 Page TRM / B 3.3-9 08/11/2016 06/20/2017 06/30/2010 10/07/2015 06/30/2010 10/31/2007 Pages TRM / B 3.3-10 through TRM / B 3.3-12 01/07/2011 Page TRM / B 3.3-13 01/21/2014 Page TRM / B 3.3-14 06/25/2002 Page TRM / B 3.3-14a 11/04/2015 Page TRM / B 3.3~14b 11/04/2015 Page TRM / B 3.3-14c 11/04/2015 Pages TRM / B 3.3-15 and TRM / B 3.3-16 10/22/2003 Page TRM / B 3.3-17 03/22/2006 Pages TRM / B 3.3-17a through TRM / B 3.3-17c 03/22/2006 Page TRM / B 3.3-17d 03/27/2008 Pages TRM / B 3.3-17e and TRM / B 3.3-17f 03/22/2006 Pages TRM / B 3.3-18 and TRM / B 3.3-19 08/03/2010 Page TRM / B 3.3-20 10/22/2003 Page TRM / B 3.3-21 05/16/2003 Pages TRM / B 3.3-22 and TRM / B 3.3-23 04/07/2009 B 3.4 REACTOR COOLANT SYSTEM BASES Page B 3.4-1 08/31/1998 Pages TRM / B 3.4-2 and TRM / B 3.4-3 04/01/2009 Pages TRM / B 3.4-4 and TRM / B 3.4-4a 10/31/2007 Page TRM / B 3.4-5 10/15/1999 Page B 3.4-6 08/31/1998 Pages TRM / B 3.4-7 and TRM / B 3.4-8 04/25/2013 SUSQUEHANNA - UNIT 1 TRM / LOES-4 EFFECTIVE DATE 12/15/2017
SUSQUEHANNA STEAM ELECTRIC STATION Rev. 93 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
- Section B 3.5 Title ECCS AND RCIC BASES Pages B 3.5-1 and B 3.5-2 Pages TRM / B 3.5-3 through TRM / B 3.5-5 Effective Date 08/31/1998 10/31/2007 B 3.6 CONTAINMENT BASES Page TRM / B 3.6-1 07/26/2001 Page TRM / B 3.6-2 02/01/1999 Page B 3.6-3 08/31/1998 Page TRM / B 3.6-4 03/27/2008 Page TRM / B 3.6-5 04/04/2007 Page TRM / B 3.6-6 12/03/2004 Pages TRM / B.3.6-7 through TRM / B 3.6-11 12/31/2002 B 3.7 PLANT SYSTEMS BASES Pages 8 3.7-1 and B 3.7-2 08/31/1998 Page TRM / 8 3.7-3 11/22/2016 Page TRM / B 3. 7-3a 11/22/2016 Page TRM / 8 3.7-4 01/26/2017 Page TRM / B 3.7-5 08/02/1999 Page TRM / B 3.7-6 03/31/2006 Pages TRM / B 3.7-7 and TRM / 8 3.7-7a 08/02/1999 Page TRM / B 3.7-8 05/29/2013 Page TRM / B 3.7-9 04/11/2014 Page TRM / B 3.7-10 08/02/1999 Page TRM / 8 3.7-10a 03/31/2006 Page TRM / 8 3.7-11 08/02/1999 Page TRM / 8 3.7-11a 03/31/2006 Pages TRM / B 3.7-12 and TRM / B 3.7-13 08/02/1999 Pages TRM / 8 3.7-14 and TRM / B 3.7-14a 09/25/2012 Page TRM / 8 3.7-14b 11/24/2011 Pages TRM / B 3.7-15 and TRM / B 3.7-16 02/01/1999 Pages B 3.7-17 through B 3.7-20 08/31/1998 Page TRM / B 3.7-21 05/29/2013 Pages TRM / B 3.7-21a through TRM / B 3.7-21d 05/24/2012 Pages TRM / B 3.7-21e through TRM / B 3.7-219 05/29/2013 Page TRM / B 3.7-22 and TRM / B 3.7-23 01/30/2008 Page TRM / B 3.7-24 - 10/05/2006 Page TRM / B 3.7-25 01/21/2014 Pages TRM / B 3.7-26 through TRM / B 3.7-28 10/05/2006 Pages TRM / B 3. 7-29 and TRM / 8 3. 7-30 06/07/2007 Page TRM / B 3. 7-30a 10/05/2006 Page TRM / B 3. 7-30b 01/21/2014 Page TRM / B 3.7-31 11/30/2011 Page TRM / B 3.7-32 03/09/2001 Page TRM / B 3.7-33 04/15/2003 Page TRM / B 3.7-34 12/03/2004 I Page TRM / 8 3. 7-35 Pages TRM / B 3.7-36 through TRM / B 3.7-39 Page TRM / B 3. 7-40 07/05/2000 04/01/2009 04/08/2010 SUSQUEHANNA - UNIT 1 TRM / LOES-5 EFFECTIVE DATE 12/15/2017
SUSQUEHANNA STEAM ELECTRIC STATION Rev.93 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
- Section B 3.8 Title ELECTRICAL POWER BASES Page TRM / B 3.8-1 Page TRM / B 3.8-2 Effective Date 04/02/2002 01/28/2005 Page TRM / B 3.8-2a 03/01/2010 Page TRM / B 3.8-3 04/02/2002 Page TRM / B 3.8-3a 04/02/2002 Page TRM / B 3.8-4 09/03/2004 Page TRM / B 3.8-4a 04/02/2002 Page B 3.8-5 08/31/1998 Pages TRM / B 3.8-6 through TRM / B 3.8-15 04/02/2002 Page TRM / B 3.8-16 11/07/2013 Page TRM / B 3.8-17 11/30/2011 Pages TRM / B 3.8-17a and TRM / B 3.8-17b 11/30/2011 Pages TRM / B 3.8-18 through TRM / B 3.8-20 05/29/2013 Pages TRM / B 3.8-21 and TRM / B 3.8-22 05/28/2009 Page TRM / B 3.8-23 05/29/2013 Page TRM / B 3.8-24 05/28/2009 B.3.9 REFUELING OPERATIONS BASES Pages B 3.9-1 through 8 3.9-7 08/31/1998
- B 3.10 MISCELLANEOUS BASES Page B 3.10-1 Pages TRM / B 3.10-2 and TRM / B 3.10-3 Pages TRM / B 3.10-4 and TRM / B 3.10-5 Page TRM / B 3.10-6 08/31/1998 03/22/2006 08/23/1999 03/27/2008 SUSQUEHANNA - UNIT 1 TRM / LOES-6 EFFECTIVE DATE 12/15/2017
SUSQUEHANNA STEAM ELECTRIC STATION Rev. 93 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
- Section B 3.11 Title RADIOACTIVE EFFLUENTS BASES Pages B 3.11-1 through B 3.11-9
- Effective Date 08/30/1998 Page TRM / B 3.11-10 02/01/1999 Pages TRM/B 3.11-11 and TRM/8 3.11-11a 04/07/2000 Pages TRM/B 3.11-12 and TRM/8 3.11-13 02/01/1999 Page TRM / B 3.11-14 12/03/2004 Page TRM / B 3.11-15 02/01/1999 Pages B 3.11-16 through B 3.11-19 08/30/1998 Page TRM / B 3.11-20 04/02/2002 Page TRM / B 3.11-20a 04/02/2002 Page TRM / B 3.11-21 05/13/2005 Pages TRM / B 3.11-22 and TRM / B 3.11-23 11/14/2006 Page~ TRM / B 3.11-23a and TRM / B 3.11-23b 06/18/2013 Pages TRM / B 3.11-24 and TRM / B 3.11-24a 08/11/2016 Page TRM / B 3.11-25 01/21/2004 Pages B 3.11-26 and B 3.11-27 08/30/1998 Page TRM / B 3.11-28 11/30/2005 Page TRM / B 3.11-29 0.2/19/2015 Pages TRM / B 3.11-30 and TRM / B 3.11-31 05/29/2013 Page TRM / B 3.11-32 08/30/1998
- B.3.12 Page TRM / B 3.11-33 Pages B 3.11-34 and B 3.11-35 Page TRM / B 3.11-36 LOADS CONTROL PROGRAM BASES Page TRM / B 3.12-1 06/30/2010 08/30/1998 02/12/1999 09/19/2007 Page TRM / B 3.12-2 11/29/2010 Page TRM / B 3.12-3 02/05/1999 SUSQUEHANNA - UNIT 1 TRM / LOES-7 EFFECTIVE DATE 12/15/2017
Core Operating Limits Report (COLR) Rev. 18 3.2.1
- 3.2 Core Operating Limits Report (COLR) 3.2.1 Core Operating Limits Report (COLR)
TRO 3.2.1 The Core Operating Limits specified in the attached COLR shall be met. APPLICABILITY: Specified in the referenced Technical Specifications. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Core Operating Limits not A.1 Perform action(s) described Specified in met. in referenced Technical referenced Specification. Technical Specifications .
- TECHNICAL REQUIREMENT SURVEILLANCE SURVEILLANCE FREQUENCY
------------------------------------NOTE---------------------~--------~------- N/A No associated Surveillances. Surveillances are implemented in the applicable Technical Specifications .
- SUSQUEHANNA - UNIT 1 TRM / 3.2-1 EFFECTIVE DATE 07/07/1999
Rev. 18 PL-NF-18-003 Rev. 0 Page 1 of 62 Susquehanna SES Unit 1 Cycle 21
- - -CORE -OPERA TING LIMITS REPORT Nuclear Fuels Engineering April 2018 SUSQUEHANNA UNIT 1 TRM/3.2-2 EFFECTIVE DATE 04/11/2018
Rev. 18
- PL-NF-18-003 Rev. 0 Page 2 of 62 CORE OPERATING LIMITS REPORT REVISION DESCRIPTION INDEX Rev. Affected No. Sections Description/Purpose of Revision *,
0 ALL Issuance of this COLR is in support of Unit 1 Cycle 21 operation.
- FORM NFP-QA-008-2, Rev. 2 SUSQUEHANNA UNIT 1 TRM/3.2-3 EFFECTIVE DATE 04/11/2018
Rev. 18 PL-NF-18-003 Rev. O Page 3 of 62 SUSQUEHANNA STEAM ELECTRIC STATION Unit 1 Cycle 21 CORE OPERATING LIMITS REPORT Table of Contents
1.0 INTRODUCTION
..........................................................................................................4 2.0 DEFINITIONS .......................... :..................................................................................5 3.0 SHUTDOWN MARGIN ................................................................................................ 6 4.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) ....................... 7 5.0 MINIMUM CRITICAL POWER RATIO {MCPR) ........................................................... 9 6.0 LINEAR HEAT GENERATION RATE (LHGR) ............................................................. 27 7.0 ROD BLOCK MONITOR (RBM) SETPOINTS AND OPERABILITY REQUIREMENTS ........................................................................................................ 38 8.0 RECIRCULATION LOOPS - SINGLE LOOP OPERATION ........................................ .40 9.0 POWER/ FLOW MAP ................................................................................................ 58 10.0 OPRM SETPOINTS ...................... '. ............................................................................. 60
11.0 REFERENCES
............................................................................................................61
- SUSQUEHANNA UNIT 1 TRM/3.2-4 EFFECTIVE DATE 04/11/2018
Rev. 18 PL-NF-18-003 Rev. 0 Page 4 of 62
1.0 INTRODUCTION
This CORE OPERATING LIMITS REPORT for Susquehanna Unit 1 Cycle 21 is prepared in accordance with the requirements of Susquehanna Unit 1, Technical Specification 5.6.5. As required by Technical Specifications 5.6.5, core shutdown margin, the core operating limits, RBM setpoints, and OPRM setpoints presented herein were developed using NRG-approved methods and are established such that all applicable limits of the plant safety analysis are met.
- SUSQUEHANNA UNIT 1 TRM/3.2-5 EFFECTIVE DATE 04/11/2018
Rev. 18 PL-NF-18-003 Rev. O
- Page 5 of 62 2.0 DEFINITIONS Terms used in this COLR but not defined in Section 1.0 of the Technical Specifications or Section 1.1 of the Technical Requirements Manual are provided below.
2.1 The AVERAGE PLANAR EXPOSURE at a specified height shall be equal to the total energy produced per unit length at the specified height divided by the total initial weight of uranium per unit length at that height. 2.2 The PELLET EXPOSURE shall be equal to the total energy produced per unit length of fuel rod at the specified height divided by the total initial weight of uranium per unit length of that rod at that height. 2.3 FDLRX is the ratio of the maximum LHGR calculated by the core monitoring system for each fuel bundle divided by the LHGR limit for the applicable fuel bundle type.
- 2.4 LHGRFACf is a multiplier applied to the LHGR limit when operating at less than 108 Mlbm/hr core flow. The LHGRFACf multiplier protects against both fuel centerline melting and cladding strain during anticipated system transients initiated from core flows less than 108 Mlbm/hr.
- 2.5 2.6 LHGRFACp is a multiplier applied to the LHGR limit when operating at less than RATED THERMAL POWER. The LHGRFACp multiplier protects against both fuel centerline melting and cladding strain during anticipated system transients initiated from partial power conditions.
MFLCPR is the ratio of the applicable MCPR operating limit for the applicable fuel bundle type divided by the MCPR calculated by the core monitoring system for each fuel bundle. 2.7 MAPRAT is the ratio of the maximum APLHGR calculated by the core monitoring system for each fuel bundle divided by the APLHGR limit for the applicable fuel bundle type. 2.8 OPRM is the Oscillation Power Range Monitor. The Oscillation Power Range Monitor (OPRM) will reliably detect and suppress anticipated stability related power oscillations while providing a high degree of confidence that the MCPR safety limit is not violated. , 2.9 Np is the OPRM setpoint for the number of consecutive confirmations of oscillation half-cycles that will be considered evidence of a stability related power oscillation. 2.10 Sp is the OPRM trip setpoint for the peak to average OPRM signal.
- 2.11 Fp is the core flow, in Mlbm / hr, below which the OPRM RPS trip is activated .
SUSQUEHANNA UNIT 1 TRM/3.2-6 EFFECTIVE DATE 04/11/2018
Rev. 18 PL-NF-18-003 Rev.a
- 3.0 SHUTDOWN MARGIN 3.1 References Page 6 of 62 Technical Specification 3.1.1 3.2 Description Tl1e SHUTDOWN MARGIN shall be equal to or greater than:
a) 0.38% Llk/k with the highest worth rod analytically determined b) 0.28% ~k/k with the highest worth rod determined by test Since core reactivity will vary during the cycle as a function of fuel depletion and poison burnup, Beginning of Cycle (BOC) SHUTDOWN MARGIN (SDM) tests must also account for changes in core reactivity during the cycle. Therefore, the SDM measured at BOC must be equal to or greater than the applicable requirement from either 3.2.a or 3.2.b plus an adder, "R". The adder, "R", is the difference between the calculated value of maximum core reactivity (that is, minimum SOM) during the operating cycle and the calculated BOC core reactivity. If the value of "R" is zero (that is, BOC is the most reactive point in the cycle) no correction to the BOC measured value is required. The SHUTDOWN MARGIN limits provided in 3.2a and 3.2b are applicable in MODES 1, 2, 3, 4, and 5. This includes core shuffling .
- SUSQUEHANNA UNIT 1 TRM/3.2-7 EFFECTIVE DATE 04/11/2018
Rev. 18 PL-NF-18-003 Rev. 0 Page 7 of 62 4.0 AVERAGE PLANAR LINEAR HEAT GENERATION RA TE {APLHGR) 4.1 References Technical Specification 3.2.1 4.2 Description The APLHGRs for ATRIUM'-10 fuel shall not exceed the limit shown in Figure 4.2-1. The APLHGR limits in Figure 4.2-1 are valid in Two Loop Operation for Main Turbine Bypass Operable and Inoperable, EOC-RPT Operable and Inoperable, Backup Pressure Regulator Operable and Inoperable, and with one Turbine Stop Valve (TSV) or Turbine Control Valve (TCV) closed. The APLHGR limits for Single Loop operation are provided in Section 8.0 . SUSQUEHANNA UNIT 1 TRM/3.2-8 EFFECTIVE DATE 04/11/2018
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n I I D a I I D D fl II I I D I g B I I I I I I 1 I I I II I I I B B I a I D I a D I I I tt I D D I I I D D I B I U I D I I I D I I I I I I I I I I I I I I I I I B I I I I I I I
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---r---~---r---r---r---T---T---T---T---~---,---,---,---~---~----,----,----,----,----r---r---r---r---r---r---T---T---T---~---~---,---,--
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~ 167000 6 9__J__ _
___l ___al___ L___ t___ t___1___1___1___ J___1___ J___ J___J___J___ J___ J_ __ _L __..L __ 1_ ___L___L___L___ l___ l___i___1u___1___ j ___J___1_._J---J-~-J: I a 1 I I I I I I I I I I I I I I B I u D I a D D I I I I m 6.0 I I I I a I I a a a I a I D I I I I I I I I I I I I I I I I I I I I I tt I D I I I a I I I a a D I D a a D D i D D D D D I u I D D D I D I D 1 I D I I I I I I I I I I I D D D I U I I D I D D U D a U a D B I D I I I I I I I I B I I I I I I I I I a I I g I g I n D I I I D D I I B I I I I B I I I I I I I I B I I I a u I I I I u D a I I B i I a U a I I I I I I I D I I I I I B I I I O U I D I I D I I D I I D I I D a u I g I I I I I I I I I I a I u I D a I u u I D I D D I D D B
---~---~---~---}-~-~---}---}---~---{---~---{---~---~---~---~----:----:----t----~---~---~---~---~---}---}---~---{---{---4---{---~---~---~---~---
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~
I I D a I I I I I I I I u I I I I I I I I I g I I n I D I D D a a D I a I I I I I I a I ! I I a II I a I I I I I D a I I I I a a I D I D D D I D u D D I a I I I I I 8 I I I I I I I I I I I I I g I U Q I R D D I n g I I I I I I D 8 D I I I I I I I I I I I I I I I I D B D U D I I D II U I I I I I I 1 I I I I I I I I I I I I I I I I I I I I i I I I I I I 4.0 0 10000 20000 30000 40000 50000 60000 70000 Average Planar Exposure (MWD/MTU) 1J 1J
!l) rI AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMIT VERSUS cc z AVERAGE PLANAR EXPOSURE - TWO LOOP OPERATION CD 71 00 ;::o --"
ATRIUM'-10 FUEL FIGURE 4.2-1 0 CD 0).
< 0f:fJ 0
NOW
Rev. 18 PL-N F-18-003 Rev. O Page 9 of 62 5.IO MINIMUM CRITICAL POWER RA TIO (MCPR) 5.1 References Technical Specification 3.2.2, 3.3.4.1, 3. 7 .6, and 3. 7 .8 Technical Requirements Manual 3.3.7 5.2 Description The MCPR limit is specified as a function of core power, core flow, average scram insertion time per Section 5.3 and plant equipment operability status. The MCPR limits for all fuel types (ATRIUM'-10) shall be the greater of the Flow-Dependent or the Power-Dependent MCPR, depending on the applicable equipment operability status. a) Main Turbine Bypass / EOC-RPT / Backup Pressure Regulator Operable Figure 5.2-1: Flow-Dependent MCPR value determined from BOC to EOG Figure 5.2-2: Power-Dependent MCPR value determined from BOC to EOG b) Main Turbine Bypass Inoperable Figure 5.2-3: Flow-Dependent MCPR value determined from BOC to EOG Figure 5.2-4: Power-Dependent MCPR value determined from BOC to EOG c) EOC-RPT Inoperable Figure 5.2-5: Flow-Dependent MCPR value determined from BOC to EOG Figure 5.2-6: Power-Dependent MCPR value determined from BOC to EOG d) Backup Pressure Regulator Inoperable Figure 5.2-7: Flow-Dependent MCPR value determined from BOC to EOG Figure 5.2-8: Power Dependent MCPR value determined from BOC to EOG e) One Turbine Stop Valve (TSV) or Turbine Control Valve (TCV) Closed Figure 5.2-9: Flow-Dependent MCPR value determined from BOC to EOG Figure 5.2-10:Power-Dependent MCPR value determined from BOC to EOG The MCPR limits in Figures 5.2-1 through 5.2-10 are valid for Two Loop
- operation .
The MCPR limits for Single Loop operation are provided in Section 8.0. SUSQUEHANNA UNIT 1 TRM/3.2-10 EFFECTIVE DATE 04/11/2018
Rev. 18 PL-NF-18-003 Rev.a Page 10 of 62 5.3 Average Scram Time Fraction If the average measured scram times are greater than the Realistic Scram times listed in Table 5.3-1 then the MCPR operating limits corresponding to the Maximum Allowable Average Scram Insertion Time must be implemented. Determining MCPR operating limits based on interpolation between scram insertion times is not permitted. The evaluation of scram insertion time data, as it relates to the attached table should be performed per Reactor Engineering procedures .
- SUSQUEHANNA UNIT 1 TRM/3.2-11 EFFECTIVE DATE 04/11/2018
Rev. 18 PL-NF-18-003 Rev.a Page 11 of 62 Main Turbine Bypass / EOC-RPT /
- _Backup Pressure Regulator Operable SUSQUEHANNA UNIT 1 TRM/3.2-'12 EFFECTIVE DATE 04/11/2018
- i.
- t SSES UNIT 1 CYCLE 21 (JJ C 2.2
(./) 0 C LEGEND m 2.1 I CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM )> z INSERTION TIME z )> 2.0 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME C z --" 1.9 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 E I I I I -; ::; 1.8
- 0 C) USED IN DETERMINING MFLCPR s:: C u) co N (l) 1.7 I c..
--" 0 u)
~
D. 0 1.6 m ~ 130, 1.531 Tl Tl m r---__ () 1.5
-~ A m ~- B 0
~ m 0 ~ 1.4 1.3 I
REFERENCE:
T.S. 3.2.2 ---- r----_ .......____
-r----_ i 108, 1.22 i N
0 --" 1.2 00 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR) MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW MAIN TURBINE BYPASS/ EOC-RPT / BACKUP PRESSURE REGULATOR OPERABLE TWO LOOP OPERATION (BOC TO EOC) FIGURE 5.2-1
(./) C 36 SSES UNIT 1 CYCLE 21 I I I I I (./) 0 ,... C ,... m 3.4 LEGEND I
)>
z CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME z 3.2 -
)> I I23, 3.06 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME -
C 23, 3.031 ~ z 3.0 \'-
-I -3,
_c I 26, 2.931 CURVE C: CORE POWER s; 26% AND CORE FLOW s; 50 MLBM/HR
\ -I -*e
- i 2.8 I26, 2.83 I 2.6 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE I
- 0
-s: e Cl) PER SR 3.7.6.1 AND 3.7.6.2 z C: (.,.) NI Cl) C. 2.4
;o ~ -3, ~
0 USED IN DETERMINING MFLCPR CD ct: ~ D. 2.2 ....>. 0 00 m :e "Tl "Tl I 26.01, 1.97 I m () 2.0 ,. ... ......
-I ...... -- ... _ 140, 1.73 < 1.8 m
CJ
~
I26.01, 1.89 I ~ - ... ... ._ --- ---- *------ . __
-....... - A 1.6 - ---
m 140, 1.64
--- I ao, 1.43 Ii 85 1.41 ---- ----- 1---------1 0 ~ - 3, -3, N
0 1.4
-J
REFERENCE:
T.S. 3.2.2 I B --- ,J ' 180, 1.41 , 85, 1.39 1100, 1.36 I 1100, 1.32 I
-3, 1.2 00 20 30 40 50 60 70 80 90 100 Core Power(% RATED) '1J '1J ru (0
rI MCPR OPERATING LIMIT VERSUS CORE POWER (D z MAIN TURBINE BYPASS/ EOC-RPT / BACKUP PRESSURE REGULATOR OPERABLE ....,. 71 vJ ;o ...>. TWO LOOP OPERATION (BOC TO EOC) 0 CD '?J FIGURE 5.2-2 -h 0).
< 00 NOW
Rev. 18 PL-N F-18-003 Rev. O Page 14 of 62 Main Turbine Bypass
- Inoperable
- SUSQUEHANNA UNIT 1 TRM/3.2-15 EFFECTIVE DATE 04/11/2018
(/) SSES UNIT 1 CYCLE 21 C 2.2 (/) 0 LEGEND C m 2.1 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME I
)>
z CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME z
)>
2.0 C z SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE
.....,. 1.9 INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 -; :::i *e 1.8 n3o, 1.751 I USED IN DETERMINING MFLCPR
- 0 C')
~ C ~
Zs ~
~ Cl) 1.7 ~
I C. 0) 0 A
~
et: B a. 0 1.6 m ::l!:
"Tl ~ ~ "Tl m
(') 1.5
< ~
m 0 1.4 ~ I108, 1.36 I
~
m I I --0
REFERENCE:
T.S. 3.7.6 and 3.2.2
~ 1.3 N
0.....,. 1.2 CX) 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR) MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW MAIN TURBINE BYPASS INOPERABLE . TWO LOOP OPERATION (BOC TO EOC) FIGURE 5.2-3
,::.:\.,. .*
-SSES UNIT 1 CYCLE 21 en C 38 en 0
C m 3.6 I )> -- z z 3.4 t---'l\..i.: 23, 3.42 1 - - - - - + - - - 1 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME -- )> C z -I 3.2 1---+\-r- -,.......- ----1----1CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME I~\ 126 3 15 1 3.03 ,1-.--1-!:==1==-----1---1 -\.
- C\.....,.\_ __...._ _ _ _----1 CURVE C: CORE POWER:::;; 26% AND CORE FLOW s; 50 MLBM/HR .....E 2.8 - - - : 26, 2.83 :1-----l-----====i=,=====,i=======i=,======F=,====i.====
-I ::::i
- a s
- Cl)
SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE -- w z C E 2.6 INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 - N Q) I Q. -\. 0 ;a 2.4 CD "" 0:: I ::: m :ii: 2.2 "Tl tl. 0 USED IN DETERMINING MFLCPR t ->. 00 "T1 I 26.01, 2.031 m 2.0 0 -...... -I r--,...__ I 40, 1.77 ' 1 - - - ~ 1 - - - - - - - + - - - - - - - - - - + - - - - - + - - - - - - 1 m 1.8
~
A 0 B - - - - - i - - - - r - - - - - :........, _ _ - - - - - . - - - - - . 11 ~ 1.6 I 80, 1.54 I 1100, 1.54 m
--i
REFERENCE:
T.S. 3. 7.6 and 3.2.2:1--1-------1------1-----+-----+----1 0 ~ - \. -\. N 0 1.4 -\. 1.2 ()) 20 30 40 50 60 70 80 90 100 Core Power(% RATED) MCPR OPERATING LIMIT VERSUS CORE POWER MAIN TURBINE BYPASS INOPERABLE TWO LOOP OPERATION (BOC to EOC) FIGURE 5.2-4
Rev. 18 PL-NF-18-003 Rev. 0 Page 17 of 62 EOC-RPT Inoperable
- SUSQUEHANNA UNIT 1 TRM/3.2-18 EFFECTIVE DATE 04/11/2018
en SSES UNIT 1 CYCLE 21 C 2.2 en 0 LEGEND C m I
)>
2.1 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM - INSERTION TIME z z
)> CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME C
2.0 - z I I
-I ....\. 1.9 .__
SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2
'§ I -I :J 1.8 ;;a C) USED IN DETERMINING MFLCPR s: C:
w :.:i E! I\.) CII 1.7 I
....\.
C. (0 0 0::: Cl. ...... 0 1.6 m :ii: 00 "Tl 130, 1.531 "Tl m r---__ 0 1.5 ._
-I A < B m
0 1.4
~ - ~
m I
REFERENCE:
T.S. 3.3.4.1 and 3.2.2 I
------ -------- ~
.0
~ . ...\. ....\. ~
1.3 r----.-__ I10s, 1.22 I 0
....\.
00 1.2 30 40 50 60 70 80 90 100
---------- 110 Total Core Flow (MLB/HR)
MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW EOC-RPT INOPERABLE TWO LOOP OPERATION (BOC TO EOC) FIGURE 5.2-5
*,i'.:'..,. "11'
(/') SSES UNIT 1 CYCLE 21 C 36 (/') 0 C LEGEND m 3.4 I )> CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM z INSERTION TIME z )> 3.2 123, 3.06 C 123, 3.031 ~ CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME z 3.0 ~ -i ,_ c J26, 2.931 CURVE C: CORE POWER s; 26% AND CORE FLOW :S: 50 MLBM/HR ~
\
I26, 2.83 1 -i
- a
- i
-.E 2.8 2.6 I
SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE s:: (.,.) N N I
~
0 CJ C: cu Cl) Q. 2.4 I . I PER SR 3.7.6.1 AND 3.7.6.2 I USED IN DETERMINING MFLCPR I I [ 0 0::: ll. 2.2 0 ,,,,m :iii!: I 26.01, 1.97 I m 2.0 () -i
'-- 140, 1.731 ~
1.8 m .............. CJ
~
A-
~B
~ m 0 .i::,. ~ ~ 1.6 1.4
~
REFERENCE:
T.S. 3.3.4.1 and 3.2.2!
-- I BO, 1.43 I 1100,1.431
~ 0 ~ 1.2 00 100 20 30 40 50 60 70 80 90 Core Power(% RATED) MCPR OPERATING LIMIT VERSUS CORE POWER EOC-RPT INOPERABLE TWO LOOP OPERATION (BOC to EOC) FIGURE 5.2-6
Rev. 18 PL-NF-18-003 Rev. 0 Page 20 of 62 Backup Pressure Regulator
- Inoperable
- SUSQUEHANNA UNIT 1 TRM/3.2-21 EFFECTIVE DATE 04/11/2018
SSES UNIT 1 CYCLE 21 en C 2.2 (./) I 0 LEGEND C m 2.1 I CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM )> z INSERTION TIME z )> 2.0 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME C z I I I I ~ ~ 1.9 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ~
'§
- J 1.8 I
ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 I I I
- o USED IN DETERMINING MFLCPR r
O') ~ C: w f!Q) [\.) 1.7 I Q. [\.) 0 ;o [\.) CD 0:: :< c.. ..... 0 1.6 m :i!: 130, 1.531 - 00 m (') ~ 1.5
------ ~
A m 0 1.4
------------ ------------ - B
~ m
IREFERENCE:
T.S. 3.7.8 and 3.2.21 0 ~ ~ ~ 1.3 ------------ r---,...__ r------. 1108, 1.221 N 0 ~ 00 1.2 30 40 50 60 70 Total Core Flow {MLB/HR) 80 90 100 1110 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW BACKUP PRESSURE REGULATOR INOPERABLE TWO LOOP OPERATION (BOC TO EOC) FIGURE 5.2-7
(/) SSES UNIT 1 CYCLE 21 C 36 (f) I 0 C LEGEND m 3.4 I
)> CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM z INSERTION TIME z )>
3.2 C I23, 3.03 23, 3.06 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME z 30 ~
-I . \ '- I26, 2.93 I CURVE C: CORE POWERS 26% AND CORE FLOWS 50 MLBM/HR ...lo. ,_ C \
2.8 :26, 2.83:
-I :J *e 2.6 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES
- a
-s: ... CJ ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 C w CIS I I I I j\J a, 2.4 : 26.01, 2.30 : N I w 0~ CL USED IN DETERMINING MFLCPR [ ll. 0 2.2 140, 2.09 I .... m :E ~ 00 "Tl "Tl m 2.0 () --....... .......A
-I < 1.8 ~
m -............_ Cl
~
m 1.6 1
REFERENCE:
T.S. 3.7.8 and 3.2.21 l8o, 1.48 I 1100, 1.36 I 0 0
~ ...lo. ...lo.
N 1.4 ...lo. 1.2 CX) 20 30 40 50 60 70 80 90 100 Core Power{% RATED) MCPR OPERATING LIMIT VERSUS CORE POWER BACKUP PRESSURE REGULATOR INOPERABLE TWO LOOP OPERATION {BOC to EOC) FIGURE 5.2-8
Rev. 18 PL-NF-18-003 Rev.a Page 23 of 62 One TSV or TCV Closed SUSQUEHANNA UNIT 1 TRM/3.2-24 EFFECTIVE DATE 04/11/2018
(/) C
** 2.2 SSES UNIT 1 CYCLE 21 en I I 0 LEGEND C
m I 2.1 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM
)>
z INSERTION TIME z)> 2.0 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME C z
-4 ...... 1.9 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES *e ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 I I I I -4 :J 1.8 ;:a s::
c:;, I!
~ .C)
C: Cl) 1.7 130, 1.72, USED IN DETERMINING MFLCPR I N I 0. ---............
~ r--,.....__
CJ1 0 0:: A
-- ~ B ....,,
C. 0 1.6 00 m :liE "Tl "Tl m ('") 1.5
~ -4 < ~
m CJ 1.4 ~ I1os, 1.371
~
m
IREFERENCE:
T.S. 3.2.2 and TRM 3.3.7 I 0
~
N 0 1.3
...... 1.2 OJ 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR)
MCPR OPERATING LIMITVERSUS TOTAL CORE FLOW ONE TSV OR TCV CLOSED"' TWO LOOP OPERATION (BOC TO EOC) FIGURE 5.2-9
"'Operation with one TSV or TCV closed is only supported at power levels S 75% rated power.
(/) SSES UNIT 1 CYCLE 21 i.r:. C 34 en I I I I 0 --- C m 3.2 LEGEND - I
)> 123, 3.06 I -
z 123,3.031 ~ CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME z 30 -
)> * ~-\., I 26, 2.93 I CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME C
z -C '\ -
-I ...),
2.8 : 26, 2.83: CURVE C: CORE POWER s 26% AND CORE FLOW s 50 MLBM/HR - I
~ 2.6 E -I :J
- 0 C'l SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE -
s;:
<.,.)
N I C: l1S a., C. 2.4 PER SR 3.7.6.1 AND 3.7.6.2
~
N 0 (j) 2.2 USED IN DETERMINING MFLCPR 0:::
- a. ......
0 00 m :!!: 2.0 I 26.01, 1.97 I "Tl "Tl ...... ...... _ m () ..........._ ...... ......
-I H ,-....... ...... 140, 1.731 1.8 26.01, 1.89 I ~ -... ........
m 0 -............ ---- -------- --------- A
)> -I 1.6 140, 1.641 -- i- . . . . _ _ _ _
175, 1.471 m ----- ----- 0
~ . ..), ...),
N -0 1.4
IREFERENCE:
T.S. 3.2.2 and TRM 3.3.71 B I75, 1.43 I
...), 1.2 00 20 30 40 50 60 70 80 Core Power(% RATED) '1J '1J ID (C
rI MCPR OPERATING LIMIT VERSUS CORE POWER CD z ONE TSV OR TCV CLOSED N 01 :::0 7l TWO LOOP OPERATION (BOC TO EOC) 0 CD Cf'
-h<O FIGURE 5.2-10 0). 0 NOW
Rev. 18 PL-NF-18-003 Rev. 0 Page 26 of 62 Table 5.3-1 Average Scram Time Fraction Table For Use With Scram Time Dependent MCPR Operating Limits Control Rod Average Scram Time to Position (seconds) Position 45 0.470 0.520 39 0.630 0.860 25 1.500 1.910 5 2.700 3.440 Average Scram Realistic Maximum Insertion Time Allowable
- SUSQUEHANNA UNIT 1 TRM/3.2-27 EFFECTIVE DATE 04/11/2018
Rev. 18 PL-NF-18-003 Rev.O Page 27 of 62 6.0 LINEAR HEAT GENERATION RA TE (LHGR) 6.1 References Technical Specification 3.2.3, 3.3.4.1, 3.7.6, and 3.7.8 Technical Requirements Manual 3.3.7 6.2 Description The maximum LHGR for ATRIUM'-10 fuel shall not exceed the LHGR limit determined from Figure 6.2-1. The LHGR limit in Figure 6.2-1 is valid for Main Turbine Bypass Operable and Inoperable, EOC-RPT Operable and Inoperable, Backup Pressure Regulator Operable and Inoperable, and with one Turbine Stop Valve (TSV) or Turbine Control Valve (TCV) closed. To protect against both fuel centerline melting and cladding strain during anticipated system transients initiated from reduced power and flow conditions, power and flow dependent LHGR limit multipliers are provided in the following figures: a) Main Turbine Bypass / EOC-RPT / Backup Pressure Regulator Operable
- b)
Figure 6.2-2: Flow-Dependent LHGR Limit Multiplier Figure 6.2-3: Power-Dependent LHGR Limit Multiplier Main Turbine Bypass or EOC-RPT or Backup Pressure Regulator Inoperable Figure 6.2-4: Flow-Dependent LHGR Limit Multiplier Figure 6.2-5: Power-Dependent LHGR Limit Multiplier c) One Turbine Stop Valve (TSV) or Turbine Control Valve (TCV) Closed Figure 6.2-6: Flow-Dependent LHGR Limit Multiplier Figure 6.2-7: Power-Dependent LHGR Limit Multiplier The LHGR limits and LHGR limit multipliers in Figures 6.2-1 through 6.2-7 are valid for both Two Loop and Single Loop operation .
- SUSQUEHANNA UNIT 1 TRM/3.2-28 EFFECTIVE DATE 04/11/2018
en C (f) 16.0 SSES UNIT 1 CYCLE 21
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Rev. 18 PL-NF-18-003 Rev.O Page 29 of 62 Main Turbine Bypass / EOC-RPT / Backup Pressure Regulator a Operable
- SUSQUEHANNA UNIT 1 TRM/3.2-30 EFFECTIVE DATE 04/11/2018
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Rev. 18 PL-NF-18-003 Rev. 0 Page 32 of 62 Main Turbine Bypass or EOC-RPT or Backup Pressure Regulator*
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- SUSQUEHANNA UNIT 1 TRM/3.2-33 EFFECTIVE DATE 04/11/2018
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< 0.50 8 I I I I I I I I I I m -r- ---r-------""r*------~--------~--------,--------,--------,--------,------ USED IN DETERMINING FDLRX 1 26, 0.48 ! i i i i i i i 23, 0.46 _____ J.. _______ ..:..I _______ .J_i _______ JI ________ JI ________ JI ________ JI ________ JI ________ JI ______ ~ . i . . . , . . , . ~ ~.... ~~~-...~~~ .... ~~~ ....~,......
1 1 1 II :I ID II II .-~- - - ~- - - - -.........' - - - ~- - - - -.........- - - - - - - - - ~ - - - - - - - - ~ - - ~ m ! I ' ! ' FOR MAIN TURBINE BYPASS INOPERABLE, SAFETY 0 0.40 126,0.39 ~-t-------t-------1-------+----- ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES
~ *
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...... I I I I I ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 ...... 23, 0.36 -----l---------l---------1---------l--------..:--------..:------~.,..-----,:-----:-----:-----,-----,,----,.----,-----,----
1 I I I I I i'3 I I I I B B I I I I I D I I I g I I 0 I I I I I I
...... 0.30 00 20 30 40 50 60 70 80 90 100 Core Power(% RATED)
POWER DEPENDENT LHGR LIMIT MULTIPLIER MAIN TURBINE BYPASS OR EOC-RPT OR BACKUP PRESSURE REGULATOR INOPERABLE ATRIUM'-10 FUEL FIGURE 6.2-5
Rev. 18 PL-NF-18-003 Rev. 0 Page 35 of 62 One TSV- or TCV Closed SUSQUEHANNA UNIT 1 TRM/3.2-36 EFFECTIVE DATE 04/11/2018
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- I I I I I I
I I I I I I I I I I I SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES m n I I I I I B I I I I I ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 0 0.40 --------:---------:---------t--------t-------i--------i------
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~ I I 8 I I I I I I I I I I I I I I I I I I ....... I I I I I I I I I I I I I I I ....... --------l---------:---------1---------1--------~--------~--------~--------~--------4--------4--------~--------~--------~--------i--------~-------- I I I I I I I I I I I I I I I ~ I I I I B I I I I I I B I I I I I I I I I I I I I I I I I I I I I II I I R n B I a I I I I 0 I I I I I I I I I I I I I I I ....... 0.30 CP 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR) FLOW DEPENDENT LHGR LIMIT MULTIPLIER ONE TSV OR TCV CLOSED* ATRIUM'-10 FUEL FIGURE 6.2-6
*Operation with one TSV or TCV closed is only supported at power levels :S 75% rated power.
en SSES UNIT 1 CYCLE 21 C 1.10 en ! 0 LEGEND __ ...,.i __________ ...,.DD __________ ..... __________ ...,D _________ _ U D U B C I I I I m I I D D __ ....III __________ ....III __________ ....IIU __________ ....III _________ _ I CURVE A: BASE CURVE )> 1.00 I I I I z a I a U I I a I z CURVE B: CORE POWER s 26% AND CORE FLOW s 50 MLBM/HR l : l I )> L----------~------------~------------~------------~------------~------------~------------~------___.---l------------1-----------4------------I----------- I I B a I n I I C I U I I z 0.90 I I B I I I U
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< 0.50 s* _~ 26, o.~s ~--------~-----------l.-----------l.-----------l.-----------1----------- ,______________.._____________......____________..________, m I ! ! ! ! ! USED IN DETERMINING FDLRX r--------*--, ~ i26, 0.45 ~-------t----------t----------t----------+----------+----------"'1.------------~~---------~~------------~--------'" I I I I I I I I I m I I B I SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES 0.40 23, 0.43 -----------~-----------~---------- ~---------- 0 I .p. I I I B I I I I I I I I ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 ~ I I I I ~ -----------~-----------~-----------~----------4------------1-'L--------------------,----------------------,---------------------_,.--------------------..,..~-------------------,-~-------------------,-~--------------'--- I I I I I I n I I n I N 0 I I I I I I I I I I I I I I I I I I I. I I I I I I n I I I I I I I K m I I I I I I I I ~ 0.30 OJ 20 30 40 50 60 10 80 Core Power(% RATED)
"U "U D> r;-
POWER DEPENDENT LHGR LIMIT MULTIPLIER co co z
"Tl ONE TSV OR TCV CLOSED (,J -....I I ;:;o _,_
ATRIUM'-10 FUEL 0 CO Cf
...... <O FIGURE 6.2-7 0). 0 NOW
Rev. 18 PL-NF-18-003 Rev. O
- - 7 .0 ROD BLOCK MONITOR (RBM) SETPOINTS AND OPERABILITY REQUIREMENTS 7.1 References Page 38 of 62 Technical Specification 3.3.2.1 7.2 Description The RBM Allowable Value and Trip Setpoints for; a) Low Power Range Setpoint, b) Intermediate Power Range Setpoint, c) High Power Range Setpoint, d) Low Power Range - Upscale, e) Intermediate Power Range - Upscale, and f) High Power Range - Upscale shall be established as specified in Table 7.2-1. The RBM setpoints are valid for Two Loop and Single Loop Operation, Main Turbine Bypass Operable and Inoperable, EOC-RPT Operable and Inoperable, Backup Pressure Regulator
- Operable and Inoperable, and with one Turbine Stop Valve (TSV) or Turbine Control Valve (TCV) closed.
The RBM system design objective is to block erroneous control rod withdrawal initiated by the operator before fuel design limits are violated. If the full withdrawal of any control rod would not violate a fuel design limit, then the RBM system is not required to be operable. Table 7.2-2 provides RBM system operability requirements to ensure that fuel design limits are not violated .
- SUSQUEHANNA UNIT 1 TRM/3.2-39 EFFECTIVE DATE 04/11/2018
Rev. 18 PL-NF-18-003 Rev.O Page 39 of 62 Table 7.2-1 RBM Setpoints Allowable Nominal Trip Function Value<1> Setpoint Low Power Range Setpoint 28.0 24.9 Intermediate Power Range Setpoint 63.0 61.0 High Power Range Setpoint 83.0 81.0
.. ,.t.. -.~, .
Low Power Range - Upscale 123.4 123.0 Intermediate Power Range - Upscale 117.4 117.0 High Power Range - Upscale 105.6 105.2 (1) Power setpoint function (Low, Intermediate, and High Power Range Setpoirits) determined in percent of RATED THERMAL POWER. Upscale trip setpoint function (Low, Intermediate, and High Power Range - Upscale) determined in percent of reference level.
- Table 7.2-2 RBM System Operability Requirements Thermal Power MCPR <2 ,3>
(% of Rated)
;:: 28 and< 90 < 1.76 ;:: 90 and< 95 < 1.47 ?. 95 < 1.68 <2> Applicable to Main Turbine Bypass Operable and Inoperable, EOC-RPT Operable and Inoperable, Backup Pressure Regulator Operable and Inoperable, and with one Turbine Stop Valve (TSV) or Turbine Control Valve (TCV) closed. <3> Applicable to both Two Loop and Single Loop Operation .
- SUSQUEHANNA UNIT 1 TRM/3.2-40 EFFECTIVE DATE 04/11/2018
Rev. 18 PL-NF-18-003 Rev. 0 Page 40 of 62 8.0 RECIRCULATION LOOPS = SINGLE LOOP OPERATION 8.1 References Technical Specification 3.2.1, 3.2.2, 3.3.4.1, 3.4.1, 3.7.6, and 3.7.8 Technical Requirements Manual 3.3.7 8.2 Description APLHGR The APLHGR limit for ATRIUM'-10 fuel shall be equal to the APLHGR Limit from Figure 8.2-1. The APLHGR limits in Figure 8.2-1 are valid in Single Loop Operation for Main Turbine Bypass Operal;>le and Inoperable, EOC-RPT Operable and Inoperable, Backup Pressure Regulator Operable and Inoperable, and with one Turbine Stop Valve (TSV) or Turbine Control Valve (TCV) closed. Minimum Critical Power Ratio Limit
- The MCPR limit is specified as a function of core power, core flow, and plant equipment operability status. The MCPR limits for all fuel types (ATRIUM'-10) shall be the greater of the Flow-Dependent or the Power-Dependent MCPR, depending on the applicable equipment operability status.
a) Main Turbine Bypass / EOC-RPT / Backup Pressure Regulator Operable Figure 8.2-2: Flow-Dependent MCPR value determined from BOC to EOG Figure 8.2-3: Power-Dependent MCPR value determined from BOC to EOG b) Main Turbine Bypass Inoperable Figure 8.2-4: Flow-Dependent MCPR value determined from BOC to EOG Figure 8.2-5: Power-Dependent MCPR value determined from BOC to EOG c) EOC-RPT Inoperable Figure 8.2-6: Flow-Dependent MCPR value determined from BOC to EOG Figure 8.2-7: Power-Dependent MCPR value determined from BOC to EOC d) Backup Pressure Regulator Inoperable
- Figure 8.2-8: Flow-Dependent MCPR value determined from BOC to EOG Figure 8.2-9: Power-Dependent MCPR value determined from BOC to EOC SUSQUEHANNA UNIT 1 TRM/3.2-41 EFFECTIVE DATE 04/11/2018
Rev. 18 PL-NF-18-003 Rev. 0 Page 41 of 62 e) One Turbine Stop Valve (TSV) or Turbine Control Valve (TCV) Closed Figure 8.2-1 O:Flow-Dependent MCPR value determined from BOC to EOG Figure 8.2-11 :Power-Dependent MCPR value determined from BOC to EOC The MCPR limits in Figures 8.2-2 through 8.2-11 are valid only for Single Loop operation. Linear Heat Generation Rate Limit The LHGR limits for Single Loop Operation are defined in Section 6.0. RSM Setpoints and Operability Requirements The RSM setpoints and operability requirements for Single Loop Operation are defined in Section 7.0 .
- SUSQUEHANNA UNIT 1 TRM/3.2-42 EFFECTIVE DATE 04/11/2018
(.I) C (/) 16.0 SSES UNIT 1 CYCLE 21 0 I I C a B I I II I II I B D n n V II "Ill m I
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n I D D a I I I I I I I I I I I I n I I B n I D D g a D D D D I I I D B B m I I u I I I g I B I I I B I I I a D n a D g u a D D n ff I D N I I I a I I I I I B I D I I I I I a D R I I I n I I I I I I I I I I I a I I I I I I I I I I I I I I I I I I I I I I D D n I I a I I I I I I I I I I I a I I G I D u U I I I g u U B I I I I I D I I I I I 0 I I n I I I I I I I I I I I ! I I I I I I I I I I I I I I a I I I !
....... 4.0 00 0.0 10000.0 20000.0 30000.0 40000.0 50000.0 60000.0 70000.0 Average Planar Exposure (MWD/MTU) "iJ "iJ m
(0 rI AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMIT VERSUS CD z AVERAGE PLANAR EXPOSURE -SINGLE LOOP OPERATION .r,.. N 71 ATRIUM'-10 FUEL 0
~ Cf 0
FIGURE 8.2-1 CJ>. 0 NO vJ
Rev. 18 PL-NF-18-003 Rev. 0 Page 43 of 62 Main Turbine Bypass / EOC-RPT /
- Backup Pressure Regulator .
Operable
- SUSQUEHANNA UNIT 1 TRM/3.2-44 EFFECTIVE DATE 04/11/2018
C Cl) (/J 3.0 SSES UNIT 1 CYCLE 21 0 LEGEND C m z I
)>
2.8 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME z)> C z 2.6 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME --- -I ...... 2.4
.E SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES
-I :J
- o 2.2 ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 -
C)
~ C w :.:. ~ I USED IN DETERMINING MFLCPR I I\.) Q) 2.0 I I I C. ;o ~ 0 0, CD 0:: :<
ll.. ...,. 0 1.8 00 m 'Tl
- e
'Tl m () 1.6 U3o, 1.ss1 -I ~ m A B 0 1.4 1100, 1.2s r m
~
0
~
0
~
1.2
REFERENCE:
T.S. 3.4.1 and 3.2.21 ...... 1.0 CX) 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR) MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW MAIN TURBINE BYPASS/ EOC-RPT / BACKUP PRESSURE REGULATOR OPERABLE SINGLE LOOP OPERATION (BOC to EOC) FIGURE 8.2-2
en C en
- 40 SSES UNIT 1 CYCLE 21 0 LEGEND C
m 3.8 I CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM )> z 3.6 INSERTION TIME z)> CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME C 3.4 z CURVE C: CORE POWER ~ 26% AND CORE FLOW ~ 50 MLBM/HR -I
~
3 *2 :::::::-123, 3.09 I
*e...
I I I 123, 3.os:~ 3 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES -I ::i *0 . C " ' I 26, 2.96 I ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2
- 0 0) s;:: :;:;s:: 2.8 26, 2.86 I
(.,.) N I ..i::,.. ca (I) C. I I USED IN DETERMINING MFLCPR CJ) 0 2.6 0::
- a. ..>.
0 m "Tl
- 1! 2.4 CX)
"Tl m 2.2 0 -I j 26.01, 2.00 I m 2.0 0 -.......... i..... ~
-.............. 140,1.76 1.8 A -s m -.a....... !60, 1.611 0
..i::,.. ~ ~ ~ 1.6 H
REFERENCE:
T.S. 3.4.1 and 3.2.2: I I
~
1100, 1.61 I 0
~ 1.4 0) 20 30 40 50 60 70 80 90 100 Core Power(% RATED)
MCPR OPERATING LIMIT VERSUS CORE POWER MAIN TURBINE BYPASS/ EOC-RPT / BACKUP PRESSURE REGULATOR OPERABLE SINGLE LOOP OPERATION (BOC to EOC) FIGURE 8.2-3
Rev. 18 PL-NF-18-003 Rev.a Page 46 of 62 Main Turbine Bypass Inoperable SUSQUEHANNA UNIT 1 TRM/3.2-47 EFFECTIVE DATE 04/11/2018
en C
};" ~IM 0 't*i,.
3.0 SSE$ UNIT 1 CYCLE 21 (/) D LEGEND C m I
)>
2.8 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM - z INSERTION TIME z)> C 2.6 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME - z -I
~
2.4 -I
*:ie 2.2 SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 ,----
- 0 C) s: C w :;:;... Ill I USED IN DETERMINING MFLCPR NI Q) 2.0 C.
~ 0 00 130, 1.781 0:::
m Tl Tl D.. 0
- 1E 1.8 00 m
() 1.6 -I m A 8 I100, 1.39 I 0 1.4 - ~ m I
REFERENCE:
T.S. 3.4.1, 3.7.6, and 3.2.2 I 0 ~ ~ ~ N 1.2 0 ~ 1.0 00 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR) MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW MAIN TURBINE BYPASS INOPERABLE SINGLE LOOP OPERATION (BOC to EOC) FIGURE 8.2-4
SSES UNIT 1 CYCLE 21 (/) C 40 I I I I I (/) 0 'LEGEND C m 3.8 I CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM )> INSERTION TIME z 3.6 z )> ~23,3.45 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME C 3.4 \ z \ CURVE C: CORE POWERS 26% AND CORE FLOW s 50 MLBM/HR -I. ..Jo. 3.2 \ r 26, 3.181 -I
- a
- J
*e 123, 3.061' 3.0 \ SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS -C VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 0)
~
~
C 2.8 I 26, 2.861 w I'll ~ Cl) I C. USED IN DETERMINING MFLCPR ~ 0 (0 2.6 a:: ll.. 0 ..... m ~ 2.4 00 m 2.2 (") -I : 26.01, 2.06 l m ......... 2.0 ...........__ 0 _ 140, 1.80 1 ~ 1.8
.......... 1 A B m 160, 1.661 0
~ ..Jo. ..Jo. ~ 0 1.6 j
REFERENCE:
T.S. 3.4.1, 3.7.6, and 3.2.2 I I100, 1.66 I ..Jo. 1.4 00 20 30 40 50 60 70 80 90 100 Core Power (% RATED) MCPR OPERATING LIMIT VERSUS CORE POWER MAIN TURBINE BYPASS INOPERABLE SINGLE LOOP OPERATION (BOC to EOC) FIGURE 8.2-5
Rev. 18 PL-NF-18-003 Rev. 0 Page 49 of 62 EOC-RPT
- Inoperable
- SUSQUEHANNA UNIT 1 TRM/3.2-50 EFFECTIVE DATE 04/11/2018
~ I SSES UNIT 1 CYCLE 21 (.I) C 3.0 (.I) 0 LEGEND C m I
)>
2.8 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM - z INSERTION TIME z
)>
C 2.6 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME - z
....l,.
2.4 I I I I
-; :J ;a '§ 2.2 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 CJ>
s: C: w :wCIS I USED IN DETERMINING MFLCPR I NI Q) 2.0 C. 01 0
....l,.
0:: a. (.) 1.8 m ~
"Tl "Tl m I30, 1.56 I
(") 1.6 m 0
~
m A 8 I108, 1.25 j 0
~ . ...l,. ....l,.
N 0 1.2
REFERENCE:
T.S. 3.4.1, 3.3.4.1, and 3.2.2 I
....l,. 1.0
()) 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR) MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW EOC-RPT INOPERABLE SINGLE LOOP OPERATION (BOC to EOC) FIGURE 8.2-6
en SSES UNIT 1 CYCLE 21 C en 40 0 C 3.8 LEGEND - m I )> z 3.6 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME z )> - C 3.4 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME - z - CURVE C: CORE POWER S 26% AND CORE FLOW s 50 MLBM/HR -I ...... 32 1 * ::::::,J 23, 3.09 - 23,3.06,~ -
~ 30 * '\."" I 26, 2.96 I
-I :i E
-c -
- 0 C) SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES -
2.8 126, 2.861
- s:: C ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 w ('G I I g I N Q) 2.6 r--
I I I C. ;o 01 0 N USED IN DETERMINING MFLCPR . CD 0:: CL 2.4 :< 0 00 m :l!: "Tl 2.2 "Tl m I 26.01, 2.00 : 0 -I m 0 2.0 1.8
- ............... 140,1.76 ....... - A B 1.6111
~ I 60, 1 m 1.6 1100, 1.61 I 0 ~ N 0 1.4 l
REFERENCE:
T.S. 3.4.1, 3.3.4.1, and 3.2.21 ...... 1.2 OJ 90 100 20 30 40 50 60 70 80 Core Power(% RATED) MCPR OPERATING LIMIT VERSUS CORE POWER EOC-RPT INOPERABLE SINGLE LOOP OPERATION (BOC to EOC) FIGURE 8.2-7
Rev. 18 PL-NF-18-003 Rev. O
- - Page 52 of 62 Backup Pressure Regulator
- - Inoperable
- SUSQUEHANNA UNIT 1 TRM/3.2-53 EFFECTIVE DATE 04/11/2018
en C (J')
- 3.0 SSES UNIT 1 CYCLE 21 D
C LEGEND m I
)>
2.8 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM z INSERTION TIME z )> C 2.6 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME z
....... 2.4 -; ::.i ;;a 'i; 2.2 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 CJ) ~ C USED IN DETERMINING MFLCPR w (II N (I) 2.0 I C. ;;o 01 0 (D +l>,
0:: D..
....l.
0 1.8 00 m ~
'Tl 'Tl m 130, 1.561
() 1.6 m 0 1.4
)> -; A j108,1.2sl m B 0 +l>,
N 0 1.2 --J
REFERENCE:
T.S. 3.4.1, 3. 7.8, and 3.2.2 1
...... 1.0 00 90 110 30 40 50 60 70 80 100 Total Core Flow (MLB/HR)
MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW BACKUP PRESSURE REGULATOR INOPERABLE SINGLE LOOP OPERATION (BOC to EOC) FIGURE 8.2-8
en C (f) 38 SSES UNIT 1 CYCLE 21 0 '---- C LEGEND m 3.6 '---- I CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM
)> '--
z INSERTION TIME z
)>
3.4 '---- CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME '---- C z 3.2 -----123, 3.09 '----
-I CURVE C: CORE POWER s 26% AND CORE FLOWS 50 MLBM/HR 123;3.06: ~ '----
3.0 '\;
... C I26, 2.96 I -I 2.8 I 26, 2.as I
- o SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES
~
w NI 0,
'§ 2.6 ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 I I I
0, ::i USED IN DETERMINING MFLCPR C, C 2.4 126.01, 2,33 I m
"Tl "Tl cu Q)
Q. 2.2
-- -- r--,......__ 140, 2.121 m 0 .............._..._
() 0::
-I ll.
0
-..............A B m
0
- l!: 2.0
-- r--,....__ --...._ : 60, 1.82:
~ 1.8
~
I100, 1.82 ! m U
REFERENCE:
T.S. 3.4.1, 3.7.8, and 3.2.2 0
~
N 0_... 1.6 1.4 CX) 20 30 40 50 . 60 70 80 90 100 Core Power(% RATED)
'"CJ '"CJ w
(0 rI MCPR OPERATING LIMIT VERSUS CORE POWER CD z BACKUP PRESSURE REGULATOR INOPERABLE 01
~;a~
71 SINGLE LOOP OPERATION (BOC to EOC) 0 CD 'f FIGURE 8.2-9 ....,< 0). 0 0 N O W
Rev. 18 PL-NF-18-003 Rev. 0 Page 55 of 62 One TSV or TCV Closed
- SUSQUEHANNA UNIT 1 TRM/3.2-56 EFFECTIVE DATE 04/11/2018
SSES UNIT 1 CYCLE 21 (f) C 3.0 (f) 0 LEGEND C m I 2.8 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM )> z INSERTION TIME z )> 2.6 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME - C z --l ...... 2.4
- t:: SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES E
--l :i
- o 2.2 ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 -
C)
- s:: C:
v) cu N Q) 2.0 I USED IN DETERMINING MFLCPR I I Q. I I ;:u 01 0 -...J CD
~ :<
ll. ....,, 0 1.8 H3o, 1.1s 1 .,,.,,m :!! - 00 m (") 1.6 --l m 1108, 1.401 A 0 1.4 B )> --l m 0 ~ N 1.2
REFERENCE:
T.S. 3.4.1, 3.2.2, and TRM 3.3. 7 I 0 ...... 1.0 00 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR) MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW ONE TSV OR TCV CLOSED* SINGLE LOOP OPERATION {BOC to EOC) FIGURE 8.2-10
*Operation with one TSV or TCV closed is only supported at power levels S 75% rated power.
,i::;.
i,.:);, (J) C
'1:,:i:*
38
. SSES UNIT 1 CYCLE 21 en D LEGEND C
m 3.6 I CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM
)>
z INSERTION TIME z 3 .4
)>
CURVE 8: REALISTIC AVERAGE SCRAM INSERTION TIME C z 3 .2
-; 123, 3.091 CURVE C: CORE POWER~ 26% AND CORE FLOW~ 50 MLBM/HR ....l.
123,3.061 ~
*e
- J 3.0 2.8
- C *"-....._ : 26, 2.9,6: "126, 2.861 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2
- a C>
s: C I w ns USED IN DETERMINING MFLCPR N I
- Q)
C. 2 .6 0, 0 ::u CD 00 0::: a. 2 .4 ....>. 0 m :!!: 00 m 2.2 C) 126.01, 2.00 I
< 2 .o m
CJ
~
140, 1.761
~
m 1.8 A- - 8 I so, 1.61 I 0
~ . ...l. ....l.
N 1.6 -J
REFERENCE:
T.S. 3.4.1, 3.2.2, and TRM 3.3.7 1 !75, 1.61 0
....l. 1.4 00 20 30 40 50 60 70 80 Core Power(% RATED)
MCPR OPERATING LIMIT VERSUS CORE POWER ONE TSVOR TCV CLOSED SINGLE LOOP OPERATION (BOC to EOC) FIGURE 8.2-11
Rev. 18 PL-NF-18-003 Rev. O Page 58 of 62 9.0 POWER/ FLOW MAP 9.1 References Technical Specification 3.3.1.1 9.2 Description Monitor reactor conditions to maintain THERMAL POWER/ core flow outside of Stability Regions I and II of the Power/ Flow map, Figure 9.1. If the OPRM Instrumentation is OPERABLE per TS 3.3.1.1, Region I of the Power/ Flow map is considered an immediate exit region. If the OPRM Instrumentation is inoperable per TS 3.3.1.1, Region I of the Power/ Flow map is considered an immediate scram region. Region II of the Power/ Flow map is considered an immediate exit region regardless of the operability of the OPRM Instrumentation .
- SUSQUEHANNA UNIT 1 TRM/3.2-59 EFFECTIVE DATE 04/11/2018
Rev. 18 PL-NF-18-003 Rev. O Page 59 of 62 120 110 110" 1riifia1, Di;!fo: ( STABILITY REGION I IF.!J_PRM ll)!OP/:Rf,E!_LE)Ml)£ti~tEi.Y' 100: ~C~M l!\W APPLICl\13_1.,E P_RO~EDUff/:. * *
.IF OPRM OPERABLE IMMEDlMELY , ,* , , , '100' ~'J)~W~PLIC~ pR~Eo.uR~ * :.*-r-1--t-1-- -*1 4 ~--:-.,,-:---:---:-._R_E_G-IO_N_ll_ _ _ _ _ _ _ _ _ _,,_~*-~r-+-t-~+- ~~-~,-,.-, ~~
JJ;.LY E!(IT l~Y,11\PPL,JC,ABJ-E @_:
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- 90
-Sit:* *. RESlRIC'TEDREGION , .
IF ABOVE MELUABOUNDARY; . _ IMMEDIAfuY,EXITIAW APPLICABLE PROCEDURE; . . . . I 1 I I I I *1 I I I I I I I I* *I
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10 ++-+-!-HH-+-+-++"'!,,-+,/f-'--+-,jHH-+--!14--:H _:?0% Speed; .i ; :_ i ; i i I , : i i : i i i 1
, , 1:0 lFFF =rq~F lF~:~== :+PtF l1=fF.:p:rF =ttl -r-T-r-T- ,.-:--r-r--r- --:--T-r--:-- -:--1--r- -T-rT-1-- r--:---:--T- -T-r-T-= .-r-+-t-+- ::,i--t-i--t- -.~t-~--~+- -+-*1--h* ;-f-i-+~+-- -r~+<t--~- ~+-+~+- *o .~,~-..,..'F'+'-t-f-'-1-1===-t-+-+-+-+-"'F'+-+-+-,r-t--:t-+-+'-+'~*....,*--'l-~'-+"~'r-1'~-+*~-~*-+-'i,--l-t'-+'-+'-'i,--1~'+-+'~-~*-+"-f-~'-+'-+'~-~*-f-~*-*~**-+-'- O*
- o *10. 20 30 :40 50 60 :70 8.0 .90 100 110 Total Core.Flow (M'ibmihr)
*(tor sLo <15% Pump: Sp~~d lise. Form G0-1 oo.-00~-2)
- SUSQUEHANNA UNIT 1 SSES Unit 1 Cycle 21 Power/ Flow Map Figure 9.1 TRM/3.2-60 EFFECTIVE DATE 04/11/2018
Rev. 18 PL-NF-18-003 Rev. O Page 60 of 62 10.0 OPRM SETPOINTS 10.1 References Technical Specification 3.3.1.1 10.2 Description Setpoints for the OPRM Instrumentation are established that will reliably detect and suppress anticipated stability related power oscillations while providing a high degree of confidence that the MCPR Safety limit is not violated. The setpoints are described in Section 2.0 and are listed below:
= 1.11 = 15 = 60 Mlbm / hr
- SUSQUEHANNA UNIT 1 TRM/3.2-61 EFFECTIVE DATE 04/11/2018
Rev. 18 PL-NF-18-003 Rev. 0 Page 61 of 62
11.0 REFERENCES
11.1 The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:
- 1. XN-NF-81-58(P)(A), Revision 2 and Supplements 1 and 2, "RODEX2 Fuel Rod Thermal-Mechanical Response Evaluation Model," Exxon Nuclear Company, March 1984.
- 2. EMF-2361(P)(A), Revision 0, "EXEM BWR-2000 ECCS Evaluation Model,"
Framatome ANP, May 2001.
- 3. EMF-2292(P)(A), Revision 0, "ATRIUM'-10: Appendix K Spray Heat Transfer Coefficients," Siemens Power Corporation, September 2000.
- 4. XN-NF-84-105(P)(A), Volume 1 and Volume 1 Supplements 1 and 2, "XCOBRA-T: A Computer Code for BWR Transient Thermal-Hydraulic Core Analysis," Exxon Nuclear Company, February 1987.
- 5. XN-NF-80-19(P)(A), Volume 1 and Supplements 1 and 2, "Exxon Nuclear Methodology for Boiling Water Reactors: Neutronic Methods for Design and Analysis," Exxon Nuclear Company, March 1983.
- 6. XN-NF-80-19(P)(A), Volumes 2, 2A, 28, and 2C "Exxon Nuclear Methodology for Boiling Water Reactors: EXEM BWR ECCS Evaluation Model," Exxon Nuclear Company, September 1982.
- 7. XN-NF-80-19(P)(A), Volume 3 Revision 2 "Exxon Nuclear Methodology for Boiling Water Reactors Thermex: Thermal Limits Methodology Summary Description," Exxon Nuclear Company, January 1987.
- 8. XN-NF-80-19(P)(A), Volume 4, Revision 1, "Exxon Nuclear Methodology for Boiling Water Reactors: Application of the ENC Methodology to BWR Reloads," Exxon Nuclear Company, June 1986.
- 9. XN-NF-85-67(P)(A), Revision 1, "Generic Mechanical Design for Exxon Nuclear Jet Pump BWR Reload Fuel," Exxon Nuclear Company, Inc.,
September 1986. 1O. ANF-524(P)(A), Revision 2 and Supplements 1 and 2, "Advanced Nuclear Fuels Corporation Critical Power Methodology for Boiling Water Reactors," November 1990.
- 11. NE-092-001A, Revision 1, "Licensing Topical Report for Power Uprate With Increased Core Flow," Pennsylvania Power & Light Company, December 1992 and NRC SER (November 30, 1993).
SUSQUEHANNA UNIT 1 TRM/3.2-62 EFFECTIVE DATE 04/11/2018
Rev. 18 PL-NF-18-003 Rev. O Page 62 of 62
- 12. ANF-89-98(P)(A) Revision 1 and Supplement 1, "Generic Mechanical Design Criteria for BWR Fuel Designs," Advanced Nuclear Fuels Corporation, May 1995.
- 13. EMF-2209(P)(A), Revision 3, "SPCB Critical Power Correlation," AREVA NP, September 2009.
- 14. EMF-85-74(P)(A), Revision 0, Supplement 1(P)(A) and Supplement 2(P)(A),
"RODEX2A (BWR) Fuel Rod Thermal-Mechanical Evaluation Model,"
Siemens Power Corporation, February 1998.
- 15. EMF-2158(P)(A), Revision 0, "Siemens Power Corporation Methodology for Boiling Water Reactors: Evaluation and Validation of CASM0-4/Microburn-B2," Siemens Power Corporation, October 1999.
- 16. EMF-CC-074(P)(A), Volume 4, Revision 0, "BWR Stability Analysis -
Assessment of STAIF with Input from MICROBURN-B2," Siemens Power Corporation, August 2000.
- 17. NED0-32465-A, "BWROG Reactor Core Stability Detect and Suppress Solutions Licensing Basis Methodology for Reload Applications," August 1996 .
- 18. ANF-913(P)(A), Volume 1 Revision 1 and Volume 1 Supplements 2, 3, and 4, "COTRANSA2: A Computer Program for Boiling Water Reactor Transient Analyses," Advanced Nuclear Fuels Corporation, August 1990.
- 19. ANF-1358(P)(A), Revision 3, "The Loss of Feedwater Heating Transient in Boiling Water Reactors," Framatome ANP, September 2005 .
- SUSQUEHANNA UNIT 1 TRM/3.2-63 EFFECTIVE DATE 04/11/2018}}